A method for manufacturing a nuclear fuel element and a nuclear fuel element includes obtaining a core, the coating of the core with an anti-diffusion layer so as to obtain a coated core, the insertion of the coated core into a cladding with interposition, between the coated core and the cladding, of one or more intermediate layer(s), and the pressing of the multilayer assembly. Each intermediate layer is being made of a ductile metal alloy and/or having a conventional yield strength which differs by no more than 30% from that of the material of the cladding, an elongation at break which differs by no more than 30% from that of the material of the cladding and/or a distributed relative elongation which differs by no more than 30% from that of the material of the cladding.
An ultrasound probe for inspecting a component at a temperature above 150° C. includes a shoe that makes contact with the component and an ultrasonic transducer. The transducer includes a probe body defining an internal volume having a body length, the probe body further defining an aperture and a disc of piezoelectric material placed in the aperture, the disc having a front side making contact with the shoe, the disc having an acoustic impedance which includes between 7 MRayl and 25 MRayl and a Curie temperature above 250° C. The transducer also includes a damper fastened to the back side of the disc and extending from the back side into the internal volume for a damper length smaller than the body length.
A plate-shaped nuclear fuel element includes a core made of a fissile material and a cladding. The cladding further includes a frame defining a central aperture receiving the core and two cover plates sandwiching the frame and the core. The frame is made of a metallic first cladding material. The cover plates are made of a metallic second cladding material. The first cladding material has a hardness strictly greater than the hardness of the second cladding material.
A method for producing a granulated metal oxide powder and corresponding granulated metal oxide powder includes obtaining an initial metal oxide powder, consisting of particles of a metal oxide, by hydrolysing a chloride of the metal and forming a suspension containing the initial metal oxide powder and an organic binder suspended in a suspension medium. The method also includes drying the suspension so as to obtain granulated metal oxide powder, consisting of grains formed by agglomerates of particles of the initial metal oxide powder.
A method for controlling a nuclear reactor includes acquiring current values of operating parameters of the reactor; and iteratively implementing the sub-steps of generating a sequence of injection of neutron poison and/or water; calculating an evolution in at least one magnitude characteristic of the state of the core of the nuclear reactor during this given time interval using a power program, current values of operating parameters and the injection sequence considered, the evolution being calculated using a predictive model of the core of the reactor; evaluating a cost function, using the calculated evolution; repeating the generating and calculating sub-steps until a convergence criterion of the cost function is met; and repeating the acquiring and the iteratively implementing steps with a time period less than 60 minutes.
G21C 7/22 - 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
G05B 13/04 - Adaptive control systems, i.e. systems automatically adjusting themselves to have a performance which is optimum according to some preassigned criterion electric involving the use of models or simulators
A method for detecting collision risks when moving a load includes the following steps:
attaching a plurality of proximity sensors around the lateral surface of the load;
lifting and moving the load using the lifting and moving equipment;
transmitting and displaying the signals generated by the proximity sensors on at least one display unit.
A method and system for accelerating the convergence of an iterative computation code of physical parameters of a multi-parameter system, in particular in the field of fluid dynamic computation. The method comprises obtaining first parameter values, of first dimensionality by applying the iterative computation code. The method further comprises applying a data dimensionality reduction on at least a part of the first parameter values of first dimensionality to compute representative second parameters of second dimensionality smaller than the first dimensionality; applying an extrapolation on at least a subset of the second parameters of second dimensionality to predict a set of predicted second parameter values, computing predicted first parameter values from the predicted second parameter values, and using the predicted first parameter values as an input data set for a new iterative computation with the iterative computation code.
G06F 9/50 - Allocation of resources, e.g. of the central processing unit [CPU]
G06F 30/28 - Design optimisation, verification or simulation using fluid dynamics, e.g. using Navier-Stokes equations or computational fluid dynamics [CFD]
A maintenance method is applied to a nuclear reactor having at least one control assembly for controlling a rod cluster assembly including a casing for receiving a lifting mechanism and a sheath for receiving the control rod, a first lip at an upper casing end and a second lip at a sheath lower end forming an omega seal. The maintenance method includes removing the first and second lips; carrying out at least one maintenance operation on the control assembly; creating a welding surface by machining said upper casing end; creating a leak-tight welded connection by welding the welding surface and a complementary welding surface provided at the lower end of the sheath or of a replacement sheath.
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
9.
FLOATING MAINTENANCE PLATFORM FOR NUCLEAR FACILITY
A platform comprises a floor comprising beams and removable slabs supported by the beams; and a floating support, arranged to float on the water filling a pool of the nuclear facility, a peripheral edge of the floor resting on the floating support. The floating support can annular and can internally define an opening. The floor can completely close the opening.
G21C 19/02 - 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
10.
DEVICE FOR USE IN A FUEL ASSEMBLY OF NUCLEAR POWER PLANT, METHOD FOR MANUFACTURING A DEVICE AND METHOD FOR ACTIVATING A MATERIAL IN A NUCLEAR POWER PLANT
The present disclosure relates to device for use in a fuel assembly of a nuclear power plant, the device comprises at least one rod, each rod comprises a plurality of containers having a space being filled with material to be activated, characterized in that the device further comprises a flow restrictor for a fuel assembly of a nuclear power plant comprising a plurality of fingers adapted to extend respectively into a control rod guide tube of the fuel assembly when the flow restrictor is inserted into the fuel assembly, wherein the at least one rod is connected to a finger of the flow restrictor, wherein the containers are arranged subsequently in a direction of the longitudinal axis of the respective rod.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
G21C 7/103 - Control assemblies containing one or more absorbants as well as other elements, e.g. fuel or moderator elements
11.
METHOD AND ELECTRONIC DEVICE FOR ASSISTING WITH SURVEILLANCE OF AN ELEMENT OF A NUCLEAR REACTOR, ASSOCIATED COMPUTER AND ASSOCIATED SYSTEM
A method for assisting with surveillance of an element of a nuclear reactor, said method being implemented by an electronic device, comprising the steps of training an artificial-intelligence algorithm; acquiring an image of the element; estimating, on the basis of the image and via the artificial-intelligence algorithm, whether a fault is present in the element; displaying the image of the element; and if at least one fault is estimated to be present, generating an alarm. In the estimating step, an input to the artificial-intelligence algorithm is an image of a region comprising the element, and an output is a level of confidence as regards an absence of fault in the element for said region. If the level of confidence is lower than a threshold, then a fault is estimated to be present. In the training step, only images of fault-free elements are inputted into the artificial-intelligence algorithm.
A method for inspecting a plurality of elements of an industrial plant includes developing an application having a user interface with a command for each element to be inspected; repeatedly acquiring image data of the elements of the industrial plant using a mobile device, and storing the image data in an acquisition memory, each image datum comprising at least one image and a timestamp indicating a time at which the image datum was acquired; activating commands at respective activation times; and associating the image data with the elements. The image data is associated with a given element being chosen exclusively from the image data having a timestamp between the time of activation of the command corresponding to said element and the time of activation of either the preceding or the following command.
G05B 19/418 - Total factory control, i.e. centrally controlling a plurality of machines, e.g. direct or distributed numerical control (DNC), flexible manufacturing systems (FMS), integrated manufacturing systems (IMS), computer integrated manufacturing (CIM)
G06F 16/58 - Retrieval characterised by using metadata, e.g. metadata not derived from the content or metadata generated manually
13.
DEVICE FOR EXTRACTING A NUCLEAR FUEL ROD OR A CLUSTER ROD AND EXTRACTION METHOD USING SUCH AN EXTRACTION DEVICE
An extraction device for extracting a nuclear fuel rod or a cluster rod comprises an attachment portion configured to be inserted into a sleeve of the rod through an end without an end plug, and a grip portion, the attachment portion comprising an elongated body along a longitudinal axis and at least one tooth projecting from the body, the or each tooth being configured to allow the attachment portion to be forcibly inserted into the sleeve axially, and to engage with the inner surface of the sleeve so as to prevent the attachment portion from being extracted from the sleeve.
An inspection system for inspecting nuclear fuel pellets comprises a supporting device for supporting the fuel pellet(s) such that the pellet axis of each fuel pellet coincides with a reference axis, and an optical measuring device arranged for optically measuring the fuel pellet(s), the optical measuring device comprising a light emitter configured for emitting a light beam propagating along an optical axis and a light detector arranged for receiving the light beam. The fuel pellet interrupts the light beam and generates a shadow projected on the light detector. The optical measuring device includes a measuring module configured for analyzing the shadow for detecting possible defects on the end faces and/or the lateral face of each fuel pellet.
A nuclear fuel rod comprises nuclear fuel contained in a cladding, the cladding comprising a tube and two plugs, the tube extending along a central axis and having two ends, each plug being attached to a corresponding end of the tube by sealing the end of the tube. The tube is covered by a tube coating extending over the entire length of the tube from one end of the tube to the other.
A method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation. The steps are being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).
G21C 3/33 - 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 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
A manufacturing method provides a nuclear reactor component comprising a substrate and a coating covering a surface of the substrate. The manufacturing method comprises laser-marking a pattern on the surface of the substrate, the marking being carried out so as to form recessed reliefs outlining the pattern in the surface of the substrate, and then applying the coating to the surface of the substrate over the pattern.
A reactor (1) for hydrolysis of uranium hexafluoride comprises a tubular injector (9) comprising first (11), second (13) and third (15) concentric fluid circulation ducts intended to be connected respectively with a source of UF6, a source of inert gas and a source of water vapor. The tubular injector (9) is obtained by additive manufacturing.
B01J 4/00 - Feed devices; Feed or outlet control devices
B01J 19/26 - Nozzle-type reactors, i.e. the distribution of the initial reactants within the reactor is effected by their introduction or injection through nozzles
A nuclear fuel cladding element comprises a substrate made of a material containing zirconium and a protective coating covering the substrate on the outside. The protective coating is being made of a material containing chromium, and has a columnar microstructure composed of columnar grains and having on the outer surface thereof a microdroplet density of less than 100 per mm2.
The invention relates to a nuclear fuel cladding produced with a substrate (14), which is made of pure zirconium or of a zirconium-based alloy, and a multilayer protective coating (16), which covers a surface (14B) of the substrate (14), the protective coating (16) comprising a main layer (18) made of pure chromium and one or more additional layers (20), each additional layer (20) being made of pure chromium or from a material consisting of chromium and, additionally, oxygen and/or nitrogen, with the optional presence of unavoidable impurities.
The invention relates to a flow calming assembly (10) for a nuclear reactor comprising a vessel (12) and an enclosure (14) situated in the vessel (12) wherein a fluid circulates from the vessel (12) to the enclosure (14) at a bottom part of the vessel (12). The flow calming assembly (10) comprises an outer calming device (28) with openings for fluid passage, the outer calming device (28) comprising an upper part (34) and a lower part (36), the upper part (34) comprising a flared or conical collar extending between an upper end (38) and a lower end (40), the lower part (36) having a shape presenting a symmetry along a main axis (D), the lower part (36) extending from the lower end (40) of the upper part (34). The invention further relates to associated reactor and installing method.
A test method is for testing a spacer grid of a nuclear fuel assembly comprising a bundle of nuclear fuel rods and N spacer grids distributed along the bundle of nuclear fuel rods, where N is a positive integer equal to or greater than four. The method of testing includes providing a test assembly comprising a bundle of test rods shorter than the nuclear fuel rods and three spacer grids distributed along the test rods, generating an impact on the centrally located spacer grid, and measuring and recording at least one impact parameter and/or at least one displacement of said centrally located spacer grid.
G21C 17/06 - Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
G21C 3/18 - Internal spacers or other non-active material within the casing, e.g. compensating for expansion of fuel rods or for compensating excess reactivity
23.
PLATFORM AND PLATFORM SYSTEM FOR NUCLEAR POWER PLANT
A platform for a nuclear power plant is configured to span a pool (4) of a nuclear power plant by being movable along two parallel rails (6) arranged on either side of the pool (4). The platform comprises at least one platform module (16) having a module floor (18) defining at least part of a platform floor (14) and two guide assemblies (20) for mating with rails (6) to guide the platform along said rails (6). Each platform module is expandable to vary the spacing between the two guide assemblies (20) of the platform module (16), the two guide assemblies (20) being close together in a storage configuration and far apart in a service configuration.
A CNC machining device (1) comprises a control console (3) and a CNC machine (5). A training assembly (33) for training operation of the CNC machining device includes a training control console (35) substantially identical to the control console (3) of the CNC machining device (1); a digital twin (36) of the CNC machine (5), comprising a simulator (37) configured to simulate the effect of commands from the training control console (35) on the CNC machine (5); and a display device (39) configured for a trainee to view the current state of the simulator (37).
G09B 19/00 - Teaching not covered by other main groups of this subclass
G05B 19/4155 - Numerical control (NC), i.e. automatically operating machines, in particular machine tools, e.g. in a manufacturing environment, so as to execute positioning, movement or co-ordinated operations by means of programme data in numerical form characterised by programme execution, i.e. part programme or machine function execution, e.g. selection of a programme
G09B 5/02 - Electrically-operated educational appliances with visual presentation of the material to be studied, e.g. using film strip
25.
Process and installation for the destruction of radioactive sodium
A radioactive sodium destruction facility includes a tank for storing liquid metallic sodium, located at a first level; a reaction vessel containing an aqueous solution; a sodium feed circuit comprising a sodium circulation member located at a second level higher than the first level, the circulation member having a suction in fluid communication with the tank and a discharge in fluid communication with the reaction vessel; an inert gas supply unit configured to supply the tank; a controller driving the sodium circulation member; and an inert gas supply unit configured to supply the tank; and a controller driving the supply unit to control a gas pressure in the tank, such that a pressure at the suction of the sodium circulation member is maintained within a predetermined range.
The plate-shaped nuclear fuel element (2) comprises a core (4) made of a fissile material and a cladding (6), the cladding comprising a frame (8) defining a central aperture (10) receiving the core (4) and two cover plates (12) sandwiching the frame (8) and the core (4), wherein the frame (8) is made of a metallic first cladding material and the cover plates (12) are made of a metallic second cladding material, the first cladding material having a hardness strictly greater than the hardness of the second cladding material.
G21G 1/02 - Arrangements for converting chemical elements by electromagnetic radiation, corpuscular radiation, or particle bombardment, e.g. producing radioactive isotopes in nuclear reactors
27.
ULTRASOUND PROBE FOR INSPECTING A COMPONENT AT A TEMPERATURE ABOVE 150°C AND ASSOCIATED INSPECTING METHOD
The present invention relates to an ultrasound probe (10) for inspecting a component at a temperature above 150°C. The probe (10) comprises a shoe (14) that makes contact with the component and an ultrasonic transducer (16). The transducer comprises: - a probe body (24) defining an internal volume (30) having a body length (LC), the probe body further defining an aperture (32); - a disc (26) of piezoelectric material placed in the aperture, the disc having a front side (38) making contact with the shoe, the disc having an acoustic impedance comprised between 7 Mrayl and 25 Mrayl and a Curie temperature above 250°C; - a damper (28) fastened to the back side (40) of the disc and extending from the back side into the internal volume over a damper length (LA) smaller than the body length (LC).
B06B 1/06 - 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
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
A BWR fuel assembly is elongated along a fuel assembly axis and comprises a lower tie plate, an upper tie plate axially spaced from the lower tie plate, a bundle of fuel rods extending axially between the lower tie plate and the upper tie plate, and a tubular fuel channel extending from the lower tie plate to the upper tie plate with encasing the fuel rods. The fuel assembly comprises an interaction device mounted on the lower tie plate and configured to interact with the fuel channel. The interaction device has an inactive configuration and an active configuration.
G21C 3/33 - 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
29.
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
30.
PROCESS AND INSTALLATION FOR THE DESTRUCTION OF RADIOACTIVE SODIUM
An installation is for the destruction of radioactive metallic sodium and includes a reaction vessel containing an aqueous solution, the reaction vessel having an aqueous solution outlet; a sodium feed circuit configured for feeding liquid metallic sodium into the reaction vessel; a liquid effluent treatment unit, comprising a drain tank and a drain line fluidically connecting the aqueous solution outlet to the drain tank; a gas treatment unit configured for diluting the gases and releasing the diluted gases into the atmosphere, the drain tank having a gas outlet fluidically connected to the gas treatment unit; an inert gas feed unit configured for feeding the drain tank.
G21C 1/02 - Fast fission reactors, i.e. reactors not using a moderator
G21C 19/18 - Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place
G21C 19/303 - Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products specially adapted for gases
31.
METHOD OF DETERMINATION OF A NUCLEAR CORE LOADING PATTERN
A method of determination of a nuclear core loading pattern defining the disposition of fuel assemblies includes definition of at least one potential core loading pattern, calculation of predictive bowing of the fuel assemblies 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 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
32.
NUCLEAR FUEL ASSEMBLY BOTTOM END PART DEBRIS FILTER AND METHOD OF MANUFACTURING SUCH A DEBRIS FILTER
A nuclear fuel assembly bottom end part debris filter has an inlet face (18A) and an outlet face (18B) opposed to the inlet face (18A) and comprises a plurality of filtering structures (50) protruding on the inlet face (18A) of the debris filter (18). Each filtering structure (50) has a structure base (52) and a structure apex (54) spaced along a structure axis (A), and each filtering structure (50) includes blades (56) distributed circumferentially around the structure axis (A). Each blade has one end connected to the structure base (52) and one end connected to the structure apex (54), and each blade (56) delimits a slot (58) with each adjacent blade (56) of the same filtering structure (50).
G21C 3/32 - 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
B33Y 80/00 - Products made by additive manufacturing
B01D 29/03 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with flat filtering elements self-supporting
B01D 29/58 - Filters with filtering elements stationary during filtration, e.g. pressure or suction filters, not covered by groups ; Filtering elements therefor with multiple filtering elements, characterised by their mutual disposition in series connection arranged concentrically or coaxially
33.
DEBRIS FILTER FOR A NUCLEAR FUEL ASSEMBLY BOTTOM END PART AND METHOD OF MANUFACTURING SUCH A DEBRIS FILTER
A debris filter configured for a nuclear fuel assembly bottom end part includes a lower nozzle (8) and the debris filter (18) is supported by the lower nozzle (8). The debris filter (18) has an inlet face (18A) and an outlet face (18B) opposed to the inlet face (18A), and comprises at least one filtering section (18D) that has a retention capacity that increases gradually or stepwise towards from the inlet face (18A) to the outlet face (18B).
A nuclear fuel assembly comprises nuclear fuel rods (4) extending along a longitudinal axis (L) and a support skeleton (6) configured to support the nuclear fuel rods (4). The support skeleton (6) includes two end pieces (8, 10), a plurality of guide tubes (12) connecting the end pieces (8, 10) to each other, and spacer grids (14) attached to the guide tubes (12), with each spacer grid (14) supporting the nuclear fuel rods (4). The nuclear fuel assembly further includes at least one reinforcement device (20) comprising at least one reinforcement plate (22) which is in contact with at least two of the guide tubes (12) and attached to one or more of the guide tubes (12) at attachment points (21). Each reinforcement plate (22) has at least two attachment points (21) that are offset relative to each other along the longitudinal axis (L).
The invention relates to a method comprising the following steps: - attaching a plurality of proximity sensors (11) around the side surface of the load (3); - lifting and moving the load (3) using the lifting and moving device (7); - transmitting and displaying the signals generated by the proximity sensors (11) on at least one display device (15).
A tubular component for a pressurised-water nuclear reactor, has the following composition by weight:
0.8%≤Nb≤2.8%;
traces≤Sn≤0.65%;
0.015%≤Fe≤0.40%; preferably 0.020%≤Fe≤0.35%;
traces≤C≤100 ppm;
600 ppm≤O≤2300 ppm; preferably 900 ppm≤O≤1800 ppm;
5 ppm≤S≤100 ppm; preferably 8 ppm≤S≤35 ppm;
traces≤Cr+V+Mo+Cu≤0.35%;
traces≤Hf≤100 ppm;
F≤1 ppm;
the remainder being zirconium and impurities resulting from production. The tubular component has an outer surface with a roughness Ra less than or equal to 0.5 μm, obtained following a final mechanical polishing step. The outer surface has a roughness Rsk≤1 in absolute value and a roughness Rku≤10.
The invention concerns a method and system for accelerating the convergence of an iterative computation code of physical parameters of a multi- parameter system, in particular in the field of fluid dynamic computation. The method comprises obtaining (12,14) first parameter values, of first dimensionality by applying the iterative computation code. The method further comprises applying (18) a data dimensionality reduction on at least a part of the first parameter values of first dimensionality to compute representative second parameters of second dimensionality smaller than the first dimensionality; applying (20) an extrapolation on at least a subset of the second parameters of second dimensionality to predict a set of predicted second parameter values, computing (22) predicted first parameter values from the predicted second parameter values, and using the predicted first parameter values as an input data set for a new iterative computation with the iterative computation code.
G06F 17/11 - 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]
38.
Method and system for using computational resources of a multiprocessor computing system
A system (1) includes a module (30) for calculating a design of experiment comprising a plurality of software tasks to be performed in order to solve a predetermined physical problem. The software tasks of the design of experiment have a first priority level. The system also includes a module (4) for scheduling the execution of software tasks by the computing system, configured to check for the presence of at least one software task with a second priority level higher than the first priority level waiting to be executed; in case of the presence of at least one such software task, obtaining freed-up computational resources for executing said at least one software task of a second priority level; in the absence of at least one such software task, allocate at least some of the software tasks of the first priority level to the available computational resources.
The inspection system comprises a supporting device (20) for supporting the fuel pellet(s) (4) such that the pellet axis (A) of each fuel pellet (4) coincides with a reference axis (B), and an optical measuring device (40) arranged for optically measuring the fuel pellet(s) (4), the optical measuring device (40) comprising a light emitter (42) configured for emitting a light beam propagating along an optical axis (C) and a light detector (46) arranged for receiving the light beam (44), wherein each fuel pellet (4) interrupts the light beam (44) and generates a shadow projected on the light detector (46), the optical measuring device (40) comprising a measuring module (48) configured for analyzing the shadow for detecting possible defects on the end faces (10) and/or the lateral face (8) of each fuel pellet (4).
The nuclear fuel rod comprises nuclear fuel contained in a cladding (4), the cladding (4) comprising a tube (6) and two end caps (8), the tube (6) extending along a central axis (A) and having two ends, each end cap (8) being fastened to a respective end of the tube (6), sealingly closing this end. The tube (6) is covered by a tube coating (16) extending over the entire length of the tube (16), from one end of the tube (6) to the other.
The method comprises the following steps:
acquisition of a plurality of quantities characterizing the operation of the nuclear reactor;
calculation of at least one critical thermal flux ratio using a deep neural network, the entries of the deep neural network being determined by using the acquired quantities, the deep neural network comprising at least two hidden layers of at least five neurons each;
calculation of the deviations between the at least one calculated critical thermal flux ratio and a plurality of predetermined reference threshold values;
formulation of a control signal for a reactor control system by using the calculated deviations, the control signal being:
automatic reactor shutdown or alarm;
do nothing;
emergency shutdown of the nuclear reactor or emission of an alarm signal if relevant.
K) of the corrective values of the commands produced by the regulator (33); and regulation of the operating parameters of the nuclear reactor, by controlling actuators using the vector (U) of the corrected values of the controls.
G21D 3/10 - 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
A nuclear fuel assembly for a boiling water reactor extends along a fuel assembly axis and includes a base including a lower tie plate, a head including an upper tie plate and a lift handle, a bundle of fuel rods extending axially between the lower tie plate and the upper tie plate, and a water channel extending within the bundle of fuel rods with axially connecting the base to the head such that the load of the base is transferred to the head via the water channel. The fuel assembly further comprises a tie rod extending between the base and the head. The tie rod is axially fixed to the base and connected to the head via a connection assembly comprising a stopping member configured to abut an abutting surface of the head for limiting a downward movement of the base relative to the head during lifting of the fuel assembly, in case of a breakage of the water channel.
G21C 3/33 - 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 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 3/328 - Relative disposition of the elements in the bundle lattice
44.
WELDING TORCH AND CORRESPONDING MANUFACTURING METHOD
A welding torch includes a head (3) having a body (11) bearing an electrode (13); an electric power source (27); and a filler metal wire (17) and a wire guide (19) guiding the filler metal wire (17) to the electrode (13). The body (11) is obtained by additive manufacturing from an electrically conductive metal, and the electrode (13) is electrically connected to the electric power source (27) by the metal constituting the body (11). The wire guide (19) includes an insulating sheath (29) inside which the filler metal wire (17) moves, and the filler metal wire (17) is electrically insulated from the potential of the body (11) by the insulating sheath (29).
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
A method comprises inserting the fuel rod (4) through the spacer grids (14) aligned along an assembling axis (A) with passing the fuel rod (4) through a lubrication chamber (30) aligned with the spacer grids (14) such that the lubrication chamber (30) is passed through by the fuel rod (4) before the insertion of the fuel rod (4) through one of the spacer grids (14), and circulating a lubrication fluid containing a gas and a lubricant in gaseous phase and/or mist form in the lubrication chamber (30). The lubrication fluid is injected in the lubrication chamber (30) at a temperature strictly higher than ambient temperature, such that lubricant deposits or condensates in liquid phase with forming a lubricant film on an external surface of the fuel rod (4) that is being inserted through said one of the spacer grids (14).
F16N 15/00 - Lubrication with substances other than oil or grease; Lubrication characterised by the use of particular lubricants in particular apparatus or conditions
A method for protecting a nuclear reactor includes reconstructing a maximum linear power density released among the fuel rods of the nuclear fuel assemblies of the core; calculating the thermomechanical state and the burnup fraction of the rods; calculating a mechanical stress or deformation energy density in the cladding of one of the rods by using the said reconstructed maximum linear power density, the calculated thermomechanical states and the calculated burnup fractions, by means of a meta-model of a thermomechanical code; comparing the calculated mechanical stress or the calculated deformation energy density with a respective threshold; and stopping the nuclear reactor if the calculated mechanical stress or the calculated deformation energy density exceeds the respective threshold.
The nuclear fuel cladding element comprises a substrate (16) made of a material based on zirconium and a protective coating (18) externally covering the substrate (16), the protective coating (18) being made of a material based on chromium, and having a columnar microstructure composed of columnar grains (20) and having on its outer surface (18B) a microdroplet density of less than 100 per mm2.
An operating facility (1) for operating a mine by in-situ leaching comprises a supply manifold (9) for supplying leach liquor to the injector well heads (3), a production manifold (15) configured to discharge leachate to a leachate treatment plant (17), a treatment manifold (19), a facility (20) for providing a treatment solution configured to inject the treatment solution into the treatment manifold (19) and/or into the supply manifold (9); and for each producing well, a production pipe (21) equipped with a production cut-off device (25) and a treatment pipe (23) equipped with a treatment cut-off device (27), fluidically connecting the corresponding producing well head (5) in parallel, respectively, to the production manifold (15) and to the treatment manifold (19).
6 supplied to the reactor (4) is between 75 and 130 kg/h, the hourly mass flowrate of dry water vapour supplied to the reactor (4) for hydrolysis is between 15 and 30 kg/h, and the temperature inside the reactor (4) is between 150 and 250° C.
B01J 4/00 - Feed devices; Feed or outlet control devices
B01J 12/00 - Chemical processes in general for reacting gaseous media with gaseous media; Apparatus specially adapted therefor
B01J 12/02 - Chemical processes in general for reacting gaseous media with gaseous media; Apparatus specially adapted therefor for obtaining at least one reaction product which, at normal temperature, is in the solid state
B01J 19/24 - Stationary reactors without moving elements inside
B01J 12/02 - Chemical processes in general for reacting gaseous media with gaseous media; Apparatus specially adapted therefor for obtaining at least one reaction product which, at normal temperature, is in the solid state
B01J 19/00 - Chemical, physical or physico-chemical processes in general; Their relevant apparatus
C01B 13/22 - Methods for preparing oxides or hydroxides in general by oxidation or hydrolysis of compounds in the gaseous state of halides or oxyhalides
51.
INSTALLATION AND METHOD FOR CONVERTING URANIUM HEXAFLUORIDE TO URANIUM DIOXIDE
An installation for the conversion of uranium hexafluoride (UF6) to uranium dioxide (UO2) comprises a hydrolysis reactor (4) for the conversion of UF6 into uranium oxyfluoride powder (UO2F2), a pyrohydrolysis furnace (6) for converting the UO2F2 powder supplied by the reactor (4) into UO2 powder, a supply device (8) comprising reagent injection ducts (10) for the injection of UF6, water vapor or H2, and a control system (16) designed to control the supply device (8) so as to supply at least one of the reagent injection ducts (10) with a neutral gas during a shut-down or start-up phase of the conversion installation.
B01J 19/26 - Nozzle-type reactors, i.e. the distribution of the initial reactants within the reactor is effected by their introduction or injection through nozzles
A nuclear reactor includes guide tubes; and vessel head penetrations each comprising a tubular adapter fixed in one of the openings and defining an inner passage. Each vessel head penetration also includes a tubular sleeve engaged in the inner passage and axially extending in line with one of the guide tubes. Each sleeve is suspended by an upper axial sleeve end lying on an upper range on the corresponding adapter. A lower axial end of the sleeve projects axially into the vessel beyond the adapter and is separated from an upper axial end of the corresponding guide tube by an axial gap having an axial height of less than 50 millimeters.
G21C 13/036 - 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 7/16 - Hydraulic or pneumatic drive arrangements
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
53.
METHOD AND FACILITY FOR CONVERTING URANIUM HEXAFLUORIDE INTO URANIUM DIOXIDE
A conversion process for converting uranium hexafluoride into uranium dioxide includes the steps of hydrolysis of UF6 to uranium oxyfluoride (UO2F2) in a hydrolysis reactor (4) by reaction between gaseous UF6 and dry water vapour injected into the reactor (4), pyrohydrolysis of UO2F2 to UO2 in a pyrohydrolysis furnace (6) by reacting UO2F2 with dry steam and gaseous hydrogen (H2) injected into the furnace (6), extracting excess gas in the reactor (4) via a collecting device (50) comprising several filters (52), periodically cleaning the filters (52) by injecting a neutral gas into the filters (52) from the outside to the inside of the reactor (4) to remove powder stuck on the filters (52), and measuring the relative pressure in the reactor (4). The conversion method further includes carrying out point cleaning of the filters (52) when the relative pressure in the reactor (4) exceeds a predetermined point cleaning threshold.
The digitally-controlled machining device (1) comprises a control console (3) and a digitally-controlled machining machine (5). The training assembly (33) comprises: - a training control console (35) substantially identical to the control console (3) of the digitally-controlled machining device (1); - a digital duplicate (36) of the digitally-controlled machining machine (5) comprising a simulator (37) configured to simulate the effect of the commands from the training control console (35) on the digitally-controlled machining machine (5); - a display device (39) configured so that an operator in training can view the current state of the simulator (37).
A method for intervention in a radioactive zone includes production of a digital model representing the three-dimensional topography of the radioactive zone (1); and intervention of the at least one operator in the radioactive zone (1). The intervention step includes repeated measurement of the radioactive radiation intensity by a portable detector (3), and determination of the spatial coordinates of the portable detector (3) at the time of the measurement; recording of a plurality of said measurements and the corresponding spatial coordinates in the digital model; materialisation of the recorded measurements in an augmented reality device (5) worn by the at least one operator, by a plurality of discrete holographie symbols (7).
An intervention device for carrying out intervention on a nuclear fuel assembly comprises an articulated robotic arm (22) comprising a securing base (26), a terminal member (28) and at least one arm segment (30, 32) connecting the base (26) to the terminal member (28), and an intervention member (24) carried by the terminal member (28). The intervention member (24) is designed to intervene on the nuclear fuel assembly (2).
B25J 9/04 - Programme-controlled manipulators characterised by movement of the arms, e.g. cartesian co-ordinate type by rotating at least one arm, excluding the head movement itself, e.g. cylindrical co-ordinate type or polar co-ordinate type
57.
Detector for high-energy radiography and associated imaging assembly
A detector (10) for high-energy radiography includes, in the following order: a metal screen (12) arranged to receive incident radiation, at least part of the incident radiation being transmitted through the metal screen and forming a transmitted radiation, a scintillator component (14) arranged to convert the radiation transmitted by the metal screen into light, and a detection layer (16) arranged to detect the intensity of the light emitted by the scintillator component. The screen (12) is made of a metal having an atomic number that is strictly greater than 70 or is made of an alloy comprising at least 50% mass content of one or more metals having an atomic number that is strictly greater than 70 and in that the thickness of the screen is between 20 μm and 900 μm.
A method is for monitoring a nuclear reactor comprising a core in which fuel assemblies are loaded, each assembly comprising nuclear fuel rods each including nuclear fuel pellets and a cladding surrounding the pellets. The method includes determining (100) at least one operating time limit (TFPPI) for the extended reduced power operation of the reduced power nuclear reactor, so as to avoid a rupture of at least one of the claddings, operating (102) the nuclear reactor at reduced power for an actual time strictly less than the time limit (TFPPI), and relaxing (104) at least one threshold for protecting the nuclear power plant as a function of a difference between the time limit (TFPPI) and the actual time.
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
59.
Programmable logic circuit for controlling an electrical facility, in particular a nuclear facility, associated control device and method
N), two distinct types of functional blocks being suitable for executing at least one distinct function, at least one processing module suitable for receiving at least one sequence (46) of functional block(s) to be executed, and at least one internal memory (38) configured to store at least said sequence (46). The programmable logic circuit (10) includes a single functional block of each type, a given functional block being suitable for being called several times, and an execution module (22) configured to execute the called functional block(s) in series, according to said sequence (46).
H03K 19/17728 - Reconfigurable logic blocks, e.g. lookup tables
H03K 19/17736 - Structural details of routing resources
H03K 19/17704 - Logic circuits, i.e. having at least two inputs acting on one output; Inverting circuits using specified components using elementary logic circuits as components arranged in matrix form the logic functions being realised by the interconnection of rows and columns
H03K 19/1776 - Structural details of configuration resources for memories
60.
Electronic device and method for simulating an ultrasonic response of a metal part, associated testing electronic system and method and computer program
k), with the computation of elementary distributions, each corresponding to an ultrasonic response received by a receiver located at a border (F) of said zone; and determining a resultant distribution of ultrasonic waves for the part with defect, from the first and second computed distributions, the resultant distribution forming a simulation of an ultrasonic response received from the part including the defect (20), in response to an ultrasonic excitation toward said part.
An anchoring device (1) for anchoring an equipment to a civil engineering structure includes a support plate (5) for the equipment, with at least two orifices (7); for each orifice (7), a longitudinal dowel (13) intended to be rigidly fastened in the civil engineering structure (3); for each orifice (7), a fastening member (25) mounted around the dowel (13); for each orifice (7), a connection (27) of the fastening member (25) to the plate (5), allowing the fastening member (25) to be placed at any given position in a defined region of the orifice (7) in a plane parallel to the plate (5); and for each orifice (7), a reversible lock (55) for blocking the fastening member (25) with respect to the plate in the given position and for blocking the fastening member in position along the dowel (13).
A subrack assembly (1) comprising a subrack (3) comprising two top rails (9), two bottom rails (7) and side elements (5), at least one rigidifying frame (21) comprising a front crossbeam, a rear crossbeam and two side beams; and at least one connector (70) for connecting the rigidifying frame (21) to the top and/or bottom of the subrack (3), comprising at least one movable block movable in translation relative to the rigidifying frame (21) between an insertion position, in which it is spaced away from the subrack (3) and a use position, in which it bears against the subrack (3). The connector (70) is configured for connecting the rigidifying frame (21) to the top and/or bottom of the subrack (3) such that the front and rear crossbeams each extend substantially parallel to a top or bottom rail (7, 9) of the subrack (3) and in alignment therewith along a vertical direction.
A tubular component of a pressurised water nuclear reactor has the following composition on a weight basis: - 0.8% = Nb = 2.8%; - traces = Sn = 0.65%; - 0.015% = Fe = 0.40%; preferably 0.020 % = Fe = 0.35 %; - traces = C = 100 ppm; - 600 ppm = O = 2300 ppm; preferably 900 ppm = O = 1800 ppm; - 5 ppm = S = 100 ppm; preferably 8 ppm = S = 35 ppm, - traces = Cr + V + Mo + Cu = 0.35%; - traces = Hf = 100 ppm; - F = 1 ppm; the balance being zirconium and fabrication impurities, and has an outer surface with a roughness Ra of not more than 0.5 µm, obtained after final mechanical polishing, characterised in that it has an outer surface with a roughness Rsk = 1 as an absolute value, and a roughness Rku = 10. A method for obtaining said component.
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
G21C 3/07 - Casings; Jackets characterised by their material, e.g. alloys
A boring assembly extends along a main axis and comprises a boring head comprising at least one first nozzle and at least one second nozzle The or each second nozzle is different from the or each first nozzle. The boring assembly includes a first delivery device configured to deliver a jet of abrasive-free water at a pressure comprised between 2000 bar and 4000 bar to the at least one first nozzle. The boring assembly includes a second delivery device configured to deliver a jet containing at least one abrasive material at a pressure comprised between 2000 bar and 6000 bar to the at least one second nozzle.
E21B 7/18 - Drilling by liquid or gas jets, with or without entrained pellets
E21B 7/16 - Applying separate balls or pellets by the pressure of the drill, so-called shot-drilling
E21B 7/24 - Drilling using vibrating or oscillating means, e.g. out-of-balance masses
E21B 21/06 - Arrangements for treating drilling fluids outside the borehole
65.
Method for determining at least one threshold value of at least one operating parameter of a nuclear reactor, and associated computer program and electronic system
A method for determining at least one threshold value of at least one operating parameter of a nuclear reactor is implemented by an electronic determination system and includes the steps of determining a first threshold value of a respective operating parameter for an operation of the reactor at a first power; and determining a second threshold value of said parameter for an operation of the reactor at a second power. The operation at the lower power of the first and second powers is an operation continued for a duration of at least 8 hours over a 24-hour sliding window. The method also includes determining a third threshold value of said parameter for an operation of the reactor at a third power between the first power and the second power.
G21D 3/10 - 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
The invention concerns a method and system for using computing resources of a computing system comprising a plurality of interconnected microprocessors designed to function in parallel, in order to perform software tasks. The system (1) comprises: - a module (30) for computing an experimental design comprising a plurality of software tasks to be performed in order to solve a physical problem defined by at least one input parameter and at least one output parameter, the experimental design being computed on the basis of a predetermined initial computational budget, the software tasks to be performed having a first priority level, - a module (4) for planning the execution of the software tasks by the computing system, configured to: - verify the presence of at least one software task with a second level of priority higher than the first level of priority waiting to be executed, - if at least one such software task is present, obtain computational resources freed up to perform the at least one software task with a second level of priority; - in the absence of at least one such software task, distributing at least some of the software tasks with the first level of priority over the available computing resources.
A cable lead-through assembly (2) includes s frame (10) delimiting a cable reception space (20); and an in-frame sub-system (11) configured for securing cables (1) to the frame (10). The in-frame sub-system (11) includes at least two plates (32) intended for extending in said cable reception space (20), the plates (32) being configured for being coupled to the frame (10) and for forming between each other at least one cable's path for at least one cable (1); securing means (14) configured for securing the or each cable (1) to a corresponding plate (32); and a locking unit (16) coupled to the frame (10). The locking unit (16) has an at-rest configuration and an operational configuration. The locking unit (16) is configured for displacing the plates (32).
H02G 3/22 - Installations of cables or lines through walls, floors or ceilings, e.g. into buildings
H02B 1/30 - Cabinet-type casings; Parts thereof or accessories therefor
H02G 3/04 - Protective tubing or conduits, e.g. cable ladders or cable troughs
H02G 3/32 - Installations of cables or lines on walls, floors or ceilings using mounting clamps
68.
Electronic device and method for managing the display of data for controlling a nuclear power plant, associated control system and computer program product
An electronic device (18) is for managing the display of data to control a nuclear power plant. The data comes from a plurality of electronic control units (16A, 16B, 16C). Each control unit is configured to perform at least one action from among acquiring a value measured by a sensor (12A, 12B, 12C) and controlling an actuator (14A, 14B, 14C), the control units, sensor(s) and/or actuator(s) being according to several different nuclear safety classes. This electronic device (18) is able to be connected to the control units, and includes a set (25) of electronic module(s) (26A, 26B, 26C) for creating overlay(s) (28A, 28B, 28C). Each overlay contains information associated with one or several control units and according to a respective safety class; and a module (30) for generating a page (32) to be displayed, by superposition of several separate overlays.
A device for detecting a defect on a surface including an optical device (14) suitable for acquiring an image of the surface in a given optical direction, a lighting device (15) comprising a plurality of light sources (16), the light sources (16) being arranged in a hemisphere (20), each light source (16) having an off and an on state, an electronic calculation device (18). The electronic calculation device (18) is able to control the optical device (14) and the lighting device (15) so that the optical device (14) acquires a plurality of images of the surface, different light sources (16) or different combinations of light sources (16) being switched on for each image, the hemisphere (20) having a diameter D smaller than or equal to 50 mm.
A tube inspection unit (10) includes an eddy current probe (14). The probe (14) has a plurality of inductors and a plurality of receivers. The receivers are magnetoresistances having a substantially linear functional zone. The inductors of the probe (14) are linked to a controller (26). The controller (26) is programmed to inject, into the inductors, a voltage with a sinusoidal component and a nonzero direct-current component, such that the receivers have a polarization center situated inside the substantially linear functional zone.
G01N 27/90 - 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
G01N 27/904 - 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 with two or more sensors
71.
NUCLEAR FUEL ASSEMBLY MANUFACTURING METHOD, NUCLEAR FUEL ASSEMBLY MANUFACTURING PLANT AND METHOD OF EXPANDING SUCH A PLANT
The method is for manufacturing a nuclear fuel assembly (2) comprising nuclear fuel rods (4) arranged in a bundle and a skeleton (6) supporting the fuel rods (4). The method comprise the steps of inserting fuel rods (4) into the skeleton (6) to obtain a fuel assembly (2) and packaging the fuel assembly (2) in view of transportation, the steps being performed in a same nuclear fuel assembly manufacturing plant (20), preferably in a same nuclear fuel assembly manufacturing building (60).
The invention relates to a method and assembly for intervention in a radioactive zone. Said method comprises the following steps: production of a digital model representing the three-dimensional topography of the radioactive zone (1); and intervention of the at least one operator in the radioactive zone (1), the intervention step comprising at least the following substeps: repeated measurement of the radioactive radiation intensity by a portable detector (3), and determination of the spatial coordinates of the portable detector (3) at the time of the measurement; recording of a plurality of said measurements and the corresponding spatial coordinates in the digital model; and materialisation of the recorded measurements in an augmented reality device (5) worn by the at least one operator, by a plurality of discrete holographic symbols (7).
A leakage testing device for testing leakage of a nuclear fuel assembly (18) by sipping. The device includes a collection assembly (32) that is configured to close an upper end (24A) of a cell (24) of a storage rack (22) for storing nuclear fuel assemblies discharged from a nuclear reactor (4). The closing prevents water contained in the cell from escaping via the upper end of the cell. The collection assembly is configured to collect products containing possible fission products released by a nuclear fuel assembly contained in the cell.
A nuclear reactor includes a vessel (1), a support plate (8), arranged in the vessel (1) above the core (2); a plurality of separate dispensing ducts (21); and support members (33) provided to keep the thermocouple ducts (21) in position. Each support member (33) includes a foot (35) rigidly attached to the support plate (8), a head (37) to which the or each thermocouple duct (21) is attached, and a detachable connection (39) from the head (37) to the foot (35).
G21C 5/02 - Moderator or core structure; Selection of materials for use as moderator - Details
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
75.
Method for inspecting a metal surface and associated device
A method for inspecting a metal surface (12) includes providing a first laser source (14) that is arranged to generate a first laser beam having a first wavelength comprised between 1000 nm and 1100 nm and a power higher than 1 W; providing a second laser source (16) that is arranged to generate a second laser beam having a second wavelength comprised between 1500 nm and 1800 nm and a power higher than 1 W; activating one of the first and second laser sources and transmitting the first or second laser beam to the entrance (22) of an optic (18); scanning the metal surface (12) with the laser beam projected by the optic; and acquiring at least one image of the infrared radiation emitted by the metal surface (12).
A method for inspecting a nuclear reactor part includes placing an optical sensor (38) in front of the part to be inspected using a carrier (40); acquiring at least a first image of at least a reference portion of the part using the optical sensor (38), the or each first image being taken with a first magnification; reconstituting a three-dimensional model of said reference portion of the part using the or each first acquired image; calculating the position of an area to be inspected relative to the optical sensor (38) using the three-dimensional model; acquiring at least a second image of the area to be inspected using the optical sensor (38), the or each second image of the area to be inspected being taken with a second magnification higher than the first magnification.
A method for calculating a PCI margin associated with a loading pattern of a nuclear reactor including a core into which fuel assemblies are loaded according to the loading pattern is implemented by an electronic system. The fuel assemblies include fuel rods each including fuel pellets of nuclear fuel and a cladding surrounding the pellets. This method includes calculating a reference principal PCI margin for a reference loading pattern of the fuel assemblies in the core; calculating a reference secondary PCI margin for the reference pattern; calculating a modified secondary PCI margin for a modified loading pattern of the fuel assemblies in the core, and calculating a modified principal PCI margin for the modified pattern, depending on a comparison of the modified secondary PCI margin with the reference secondary PCI margin.
G21C 19/20 - Arrangements for introducing objects into the pressure vessel; Arrangements for handling objects within the pressure vessel; Arrangements for removing objects from the pressure vessel
78.
Method for detecting a defect on a surface by multidirectional lighting and associated device
A method for detecting a defect on a surface (12) by multidirectional lighting includes acquiring a plurality of images of the surface (12) using an optical device (14) having an optical axis, each image being acquired with a lighting of the surface along a lighting direction (E, E′) given for each point of the surface (12) and an optical direction (O), the images being acquired with different lighting directions (E, E′) or different combinations and/or with different optical directions (O); for each point, calculating a plurality of parameters, the parameters including coefficients of an equation characterizing the response of said point of the surface as a function of the lighting direction (E, E′) and an observation direction (B, B′); and deducing from the calculated parameters whether the surface (12) has a defect at said point.
A repair device for underwater repair of a hole in a nuclear reactor part includes a holder (32), a cutting tool (22) held by the holder (32) and having at least one cutting tooth (70) for remachining an inner surface of the hole. The cutting tool (22) has a suction channel (44) extending into the cutting tool (22) between at least one inlet opening (46) and at least one outlet opening (48), a drive shaft (34) for rotating the cutting tool (22), the drive shaft (34) being held by the holder (32), and a suction tube (36) connected to the holder (32) and fluidly connected to the outlet opening (48) of the suction channel (44).
B23D 77/14 - Reamers for special use, e.g. for working cylinder ridges
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 5/06 - Means for locating or supporting fuel elements
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
An absorber cluster for a nuclear reactor includes at least a first absorber assembly and a second absorber assembly. Each absorber assembly respectively comprises neutron absorbing elements. Absorber elements of each of the first absorber assembly and the second absorber assembly are made from the same material or the same combination of materials selected from the group of neutron absorbing materials consisting of a first europium hafnate, a second europium hafnate, a first samarium hafnate, a second samarium hafnate, hafnium carbide, and samarium hexaboride. The first europium hafnate and the second europium hafnate have different compositions. The first samarium hafnate and the second samarium hafnate have different compositions. The absorber elements of the first absorber assembly have a cross-sectional structure different to that of the absorber elements of the second absorber assembly.
G21C 7/24 - Selection of substances for use as neutron-absorbing material
G21C 7/117 - Clusters of control rods; Spider construction
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
81.
DETECTOR FOR HIGH-ENERGY RADIOGRAPHY AND ASSOCIATED IMAGING ASSEMBLY
A detector (10) for high-energy radiography comprising, in this order: - a metal screen (12) arranged to receive incident radiation, at least part of the incident radiation being transmitted through the metal screen and forming transmitted radiation; - a scintillator component (14) arranged to convert the radiation transmitted by the metal screen into light; and - a detection layer (16) arranged to detect the intensity of the light emitted by the scintillator component. The screen (12) is made of a metal having an atomic number that is strictly greater than 70 or is made of an alloy comprising at least 50% mass content of one or more metals having an atomic number that is strictly greater than 70 and in that the thickness of the screen is between 20 µm and 900 µm.
The invention concerns a programmable logic circuit (10) for controlling an electrical facility, in particular a nuclear facility, the programmable logic circuit including a functional unit (14) comprising: - a plurality of types of functional block (FB1, FBi, FBN), two distinct types of functional block being suitable for executing at least one distinct function, - at least one processing module suitable for receiving at least one sequence (46) of functional blocks to be executed, - at least one internal memory (38) configured to store at least said sequence (46). According to the invention, the programmable logic circuit (10) comprises a single functional block of each type, a given functional block being suitable for being called several times, and an execution module (22) configured to execute the called functional block or blocks in series, according to said sequence (46).
A method of producing a nuclear fuel product includes the steps of providing a core comprising aluminium and low-enriched uranium; and sealing said core in a cladding. The low-enriched uranium has a proportion of U235 below 20 wt %. The step of providing the core including melting low-enriched uranium and aluminium in a furnace to form a melt of uranium-aluminium alloy, producing a powder from the melt of uranium-aluminium alloy, and cold-spraying the powder on a surface of the cladding.
B22F 9/04 - Making metallic powder or suspensions thereof; Apparatus or devices specially adapted therefor using physical processes starting from solid material, e.g. by crushing, grinding or milling
B22F 5/00 - Manufacture of workpieces or articles from metallic powder characterised by the special shape of the product
The invention relates to a tube inspection unit (10) comprising an eddy current probe (14), said probe (14) having a plurality of inductors and a plurality of receivers. The receivers are magnetoresistors having a substantially linear functional zone. The inductors of the probe (14) are linked to a controller (26). The controller (26) is programmed to inject into the inductors a voltage with a sinusoidal component and a non-zero direct-current component, such that the receivers have a polarization centre situated inside the substantially linear functional zone.
G01N 27/904 - 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 with two or more sensors
85.
METHOD FOR INSPECTING A METAL SURFACE AND ASSOCIATED DEVICE
The invention relates to a method for inspecting a metal surface (12). The method comprises the following steps: providing a first laser source (14) that is arranged to generate a first laser beam having a first wavelength comprised between 1000 nm and 1100 nm and a power higher than 1 W; providing a second laser source (16) that is arranged to generate a second laser beam having a second wavelength comprised between 1500 nm and 1800 nm and a power higher than 1 W; activating one of the first and second laser sources and transmitting the first or second laser beam to the entrance (22) of an optic (18); scanning the metal surface (12) with the laser beam projected by the optic; acquiring at least one image of the infrared radiation emitted by the metal surface (12).
The invention relates to a nuclear fuel cladding comprising: i) a substrate containing a zirconium-based inner layer, optionally coated with at least one intermediate layer formed by at least one intermediate material selected from among tantalum, molybdenum, tungsten, niobium, vanadium, hafnium or the alloys thereof; and ii) at least one protective outer layer placed on the substrate and formed by a protective material selected from either chromium or an alloy of chromium. The nuclear fuel cladding produced using the method of the invention has improved resistance to oxidation/hydriding. The invention also relates to the method for the production of the nuclear fuel cladding by ion etching of the surface of the substrate and deposition of the outer layer on the substrate with a high power impulse magnetron sputtering method (HiPIMS), as well as to the use thereof to protect against oxidation and/or hydriding.
G21C 21/02 - Manufacture of fuel elements or breeder elements contained in non-active casings
G21C 3/07 - Casings; Jackets characterised by their material, e.g. alloys
C23C 14/35 - Sputtering by application of a magnetic field, e.g. magnetron sputtering
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
C23C 14/02 - Pretreatment of the material to be coated
G21C 3/20 - Constructional details - Details of the construction within the casing with non-active interlayer between casing and active material
87.
HEAT EXCHANGER AND, IN PARTICULAR, CONVEX-BOTTOMED STEAM GENERATOR
The steam generator (1) comprises an outer casing (2) with an axis (8) that is in a vertical disposition when the heat exchanger is in service, a bundle of tubes having straight portions that are parallel to one another and to the axis (8) of the heat exchanger (1) inside the outer casing (2), at least one tube plate (4) having through holes, each receiving the end of a tube of the bundle, and at least one water chamber having a wall (6) that is circularly symmetrical about the axis (8) of the heat exchanger (1), the water chamber being fixed to the tube plate (4) at the bottom of the heat exchanger. The surface (14a) of the solid bottom (14) of the heat exchanger includes at least one central point disposed substantially on the axis of the heat exchanger (1) at a highest level relative to the set of points constituting the inside surface (14a) of the bottom (14) of the heat exchanger. The set of points constituting the inside surface (14a) of the bottom (14) is situated above a conical surface (23) having an apex point at the highest level central point of the inside surface (14a) of the bottom (14), an axis parallel to the axis (8) of the heat exchanger, and a half-angle at the apex of about 80°.
F28D 7/12 - Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged one within the other, e.g. concentrically the surrounding tube being closed at one end, i.e. return type
F22B 1/02 - Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
F28D 7/06 - Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits having a single U-bend
F28D 7/16 - Heat-exchange apparatus having stationary tubular conduit assemblies for both heat-exchange media, the media being in contact with different sides of a conduit wall the conduits being arranged in parallel spaced relation
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