AREVA NP Patent applications |
Patent application number | Title | Published |
20160090277 | SECURED GRIPPING SYSTEM - A lifting beam is provided. The lifting beam includes a lower beam and an upper beam arranged above the lower beam; an arranger for arranging the beams in close and releasable engagement with one another; and systems for gripping the load. The gripping systems are kept in an open position when the beams are in engagement with one another, and in a closed position when an engager is released. | 03-31-2016 |
20160042823 | METHODS FOR SIMULATING THE FLOW OF A FLUID IN A VESSEL OF A NUCLEAR REACTOR AND FOR CALCULATING THE MECHANICAL DEFORMATION OF ASSEMBLIES OF A NUCLEAR REACTOR CORE, AND ASSOCIATED COMPUTER PROGRAM PRODUCTS - A method for simulating the flow of a fluid in a vessel of a nuclear reactor is provided. The nuclear reactor includes the vessel and a core inside the vessel, the core including nuclear fuel assemblies, each one extending in an axial direction, including nuclear fuel rods and a grid for maintaining the rods, and being spaced apart from another by a clearance between the grids in a transverse direction. | 02-11-2016 |
20160042822 | Methods for Simulating the Flow of a Fluid in a Vessel of a Nuclear Reactor and for Calculating the Mechanical Deformation of Assemblies of a Nuclear Reactor Core, and Associated Computer Program Products - A method for simulating the fluid flow in a vessel of a nuclear reactor is provided. The reactor includes a core inside the vessel, the core including a lower plate, an upper plate and fuel assemblies extending between the plates, and having a volume axially delimited by first and second interfaces corresponding to the plates. | 02-11-2016 |
20160024626 | STAINLESS STEEL FOR HOT FORGING AND HOT FORGING METHOD USING SAID STEEL - A micro-alloyed austenitic stainless steel for hot forging is provided. The micro-alloyed austenitic stainless steel has the following composition in weight %: 16.0%≦Cr≦25.0%; 8.0%≦Ni≦25.0%; traces≦Mo≦6.0%; traces≦C≦0.08%; traces≦Si≦1.0%; traces≦Mn≦3.0%; traces≦P 21 0.045%; traces≦S≦0.035%; traces≦Cu≦2.0%; traces≦N≦0.2%; traces≦V≦0.3%; traces≦Ti≦0.3%; traces≦B≦0.005%; traces≦W≦3.0%; 0.015%≦Nb≦0.100%, the remainder being iron and inevitable manufacturing impurities. | 01-28-2016 |
20150354030 | TREATMENT PROCESS FOR A ZIRCONIUM ALLOY, ZIRCONIUM ALLOY RESULTING FROM THIS PROCESS AND PARTS OF NUCLEAR REACTORS MADE OF THIS ALLOY - A treatment process for a zirconium alloy is provided. The process includes the following steps:
| 12-10-2015 |
20150348657 | ANCHOR DEVICE AND NUCLEAR FACILITY COMPRISING SUCH AN ANCHOR DEVICE - An anchor device and a nuclear facility comprising such an anchor device are provided. This anchor device comprises a female part and a male part, the female part comprising a groove extending along a longitudinal axis, the groove having a width which decreases longitudinally and a transverse section, the male part comprising a slider with a shape mating that of the groove and able to be longitudinally inserted into the groove, the transverse section of the groove being configured so as to prevent the extraction of the slider out of the groove transversely to the longitudinal axis. The anchor device comprises a locking device able to prevent the slider from longitudinally sliding out of the groove. | 12-03-2015 |
20150310941 | NUCLEAR FUEL ASSEMBLY HAVING VARYING SPACING BETWEEN FUEL RODS - A nuclear fuel assembly having varying spacing between fuel rods is provided. The nuclear fuel assembly includes a bundle of fuel rods. The fuel rods are arranged in a first lattice with a non-uniform pitch between the fuel rods in the lowermost section of the fuel assembly and in a second lattice with a uniform pitch between the fuel rods in the uppermost section of the fuel assembly. | 10-29-2015 |
20150287481 | FUEL ROD SUPPORT INSERT FOR A NUCLEAR FUEL ASSEMBLY SPACER GRID, SPACER GRID AND NUCLEAR FUEL ASSEMBLY - A fuel rod support insert for a nuclear fuel assembly spacer grid, a spacer grid and a nuclear fuel assembly are provided. The support insert is for a nuclear fuel assembly spacer grid comprising interlaced straps defining a lattice of cells for receiving fuel rods, the insert being adapted to be secured to the straps for extending in at least one cell. The insert extends along an axis intended to be parallel to that of a cell and comprises two axially spaced end portions for connecting the insert to the straps and at least one elongated blade-like spring extending axially between the end portions for supporting a fuel rod. The spring has a non-rectilinear cross-section in each plane perpendicular to the insert axis. | 10-08-2015 |
20140247915 | METHOD FOR PRODUCING A WEAR-RESISTANT AND CORROSION-RESISTANT STAINLESS STEEL PART FOR A NUCLEAR REACTOR, CORRESPONDING PART AND CORRESPONDING CONTROL CLUSTER - A method for producing a wear-resistant and corrosion-resistant stainless steel part for a nuclear reactor is provided. This method comprises steps of providing a blank in stainless steel; shaping the blank; finishing the blank to form the part in stainless steel, the finishing step allowing the prevented onset or the removal of work hardness on the outer surface of the part; hardening the outer surface of the part via diffusion of one or more atomic species. | 09-04-2014 |
20140072091 | STRIP FOR A NUCLEAR FUEL ASSEMBLY SPACER GRID - The strip is of the type comprising a wall portion for delimiting a cell for receiving a fuel rod and allowing flow of a coolant upwardly through the spacer grid, a spring provided on the wall portion for biasing a fuel rod extending through the cell away from the wall portion, the spring being cut out in the strip and delimited by a slot and a motion limiter formed in the strip on the wall portion to limit motion of a fuel rod received in the cell towards the wall portion against action of the spring. According to one aspect of the invention, the motion limiter is located on an edge of the slot opposite the spring and defines a risen portion on the edge. | 03-13-2014 |
20140064435 | NUCLEAR FUEL ASSEMBLY FOR BOILING WATER REACTOR COMPRISING A FUEL CHANNEL SPACER - A nuclear fuel assembly for boiling water reactor is provided. The nuclear fuel assembly includes a base, a head, a bundle of fuel rods extending longitudinally between the base and the head, a tubular fuel channel encasing the bundle of fuel rods, and at least one fuel channel spacer for transversely spacing the fuel assembly from an adjacent element. The or each fuel channel spacer includes a support having at least one plate and at least one corresponding leaf spring supported by the corresponding plate, the or each plate being fixed to a corresponding sidewall of the fuel channel. | 03-06-2014 |
20140064428 | LOWER NOZZLE FOR USE IN NUCLEAR FUEL ASSEMBLY - A lower nozzle for use in a nuclear fuel assembly provided. The lower nozzle is of the type having an axis and comprising a transverse lower tie plate for channelling the coolant through the lower tie plate and a tubular skirt extending axially from the periphery of the lower tie plate, the skirt delimiting an axial housing closed at one end by the lower tie plate and open at the opposite end, a debris filter configured for axial insertion in the housing and snap-fit springs for retaining the debris filter in the housing after insertion. The springs are configured to shift the debris filter axially towards the lower tie plate. | 03-06-2014 |
20140056398 | STRIP FOR A NUCLEAR FUEL ASSEMBLY SPACER GRID - The strip is of the type comprising a wall portion for delimiting a cell with interlaced strips, a spring formed in the strip and provided on the wall portion for biasing a fuel rod extending through the cell away from the wall portion, the spring comprising a cantilevered tab formed in the strip and a contact portion formed at least partially in the tab and protruding from the tab for contacting a fuel rod received in the cell. | 02-27-2014 |
20140056397 | DEBRIS FILTER FOR NUCLEAR REACTOR INSTALLATION AND NUCLEAR FUEL ASSEMBLY COMPRISING SUCH A DEBRIS FILTER - A debris filter for a nuclear reactor installation is provided. The debris filter comprises a plurality of plates arranged side-by-side in a spaced relationship and delimiting between them flow passages extending through the debris filter from a lower inlet face to an upper outlet face of the debris filter, each passage having an intermediate section offset with respect to an inlet section and an outlet section. At least one of the plates is formed with debris catching features distributed along the plate and protruding into at least one passage delimited by the plate. | 02-27-2014 |
20140047692 | METHOD OF REPAIRING A PRESSURISER, AND EQUIPMENT FOR IMPLEMENTING THE METHOD - A method for working on a defective heating element of a pressuriser comprising a tank lying flat along a longitudinal axis and elongate heating elements extending within the tank, and at least one spacer plate through which the heating elements pass and which is capable of maintaining a transverse spacing between the heating elements is provided. The method includes cutting at least one spacer plate around the heating element so as to detach said heating element from said spacer plate, and then extracting the heating element from the tank in one single piece. | 02-20-2014 |
20140003580 | PHOTONIC SPECTROMETRY DEVICE, CORRESPONDING METHOD, AND USE OF THE DEVICE | 01-02-2014 |
20140003579 | PHOTONIC SPECTROMETRY DEVICE AND METHOD, METHOD FOR CALIBRATING THE DEVICE, AND USE OF THE DEVICE | 01-02-2014 |
20130315364 | DEVICE FOR TURNING A CONTAINER, PARTICULARLY FOR NUCLEAR FUEL ASSEMBLY, TURNING ASSEMBLY, AND NUCLEAR POWER PLANT - A device for turning a container about a turning axis is provided. The device includes a stationary holding member and two bearing members which are spaced apart along the turning axis on each side of a space for receiving a container, and which are capable of being used for bearing on the container while enabling the rotation of the container about the turning axis relative to the bearing members. The device includes a movable holding member that is mounted onto the stationary holding member so as to rotate about the turning axis, at least one bearing member being supported by the movable holding member while being mounted onto the movable holding member so as to rotate about the drive axis, the or each bearing member supported by the movable holding member not rotating about the turning axis relative to the stationary holding member when the movable holding member rotates about the turning axis relative to the stationary holding member. | 11-28-2013 |
20130251089 | NUCLEAR FUEL ASSEMBLY SPACER GRID AND CORRESPONDING NUCLEAR FUEL ASSEMBLY - A nuclear fuel assembly spacer grid defining a lattice of cells for receiving fuel rods is provided. The spacer grid includes a peripheral band composed of at least one peripheral strip delimiting a portion of the peripheral contour of the spacer grid, and at least one spacer grid positioning spring elastically deformable and formed in the peripheral band. | 09-26-2013 |
20130221662 | ASSEMBLY COMPRISING A FIRST CONDUIT AND A SECOND CONDUIT CONNECTED THROUGH A CONNECTING DEVICE - An assembly is provided that includes at least one first conduit and at least one second conduit connected together through a connecting device. The connecting device includes an exteriorly threaded tube; a connecting part attached to one end of the tube and including an orifice; a holding nut screwed onto the tube and axially maintaining the connecting part relative to a tube; and a retaining member attached on the holding nut and engaging with the first conduit so as to axially retain the first conduit fitted into the orifice, the retaining member cooperating with the first conduit so as to oppose the unscrewing of the holding nut. | 08-29-2013 |
20130195237 | METHOD FOR CONTROLLING THE POSITIONS OF NUCLEAR FUEL ASSEMBLIES INSIDE A NUCLEAR REACTOR CORE, AND CORRESPONDING CONTROL ASSEMBLY - A method for controlling the positions of a plurality of nuclear fuel assemblies ( | 08-01-2013 |
20130177124 | DEVICE FOR THE DRY HANDLING OF NUCLEAR FUEL ASSEMBLIES - A device for the dry handling of nuclear fuel assemblies is provided. The device includes a transfer basket which can be connected to a lifter and which includes a gripper for gripping the fuel assembly to be transferred, the gripper being supported by a lift built into the basket; and an indexing table which can be placed on a cask and which comprises a positioner for positioning the basket over a slot in the cask. | 07-11-2013 |
20130177121 | METHOD OF DETERMINING AT LEAST ONE TECHNOLOGICAL UNCERTAINTY FACTOR FOR NUCLEAR FUEL ELEMENTS, AND CORRESPONDING METHODS OF DESIGNING, FABRICATING, AND INSPECTING NUCLEAR FUEL ELEMENTS - The invention relates to a method of determining at least one technological uncertainty factor in respect of nuclear fuel elements ( | 07-11-2013 |
20130170599 | ASSEMBLY AND METHOD FOR INJECTING WATER CONTAINING A NEURTON-ABSORBING ELEMENT TO COOL A NUCLEAR REACTOR CORE IN A CRISIS SITUATION - An assembly is provided including a mobile structure including a main pipe equipped with a first end intended to be connected to a water supply and a second end intended to be connected to a circuit connected to the primary circuit of the reactor, and including between these two ends in the direction of circulation of the water, a pump, a water heating device, an injector for continuously injecting the powdered neutron-absorbing element into the water of the main pipe, a first mixer for mixing and dissolving powder with water and a controller driving and controlling the flow rate of the water and the flow rate of the powder injected. | 07-04-2013 |
20130163712 | BWR NUCLEAR FUEL ASSEMBLY WITH SNAP-IN SLEEVE SPRING - A nuclear fuel assembly is provided for a boiling water reactor. The nuclear fuel assembly includes a base, a head, and a bundle of full length fuel rods and partial length fuel rods, said bundle extending upwardly and longitudinally from the base to the head. The nuclear fuel assembly includes at least one clamp for longitudinally retaining a lower plug of a partial length fuel rod with respect to the base. The clamp is an additional part fitted to the base, the clamp is at least partially received in a housing provided in the base, and the clamp is assembled to the base by mechanical engagement of complementary assemblies. | 06-27-2013 |
20130108002 | SHUT-OFF DEVICE FOR A NUCLEAR REACTOR FLUID DUCT, IN PARTICULAR FOR A STEAM GENERATOR BOTTOM DRAIN | 05-02-2013 |
20120279965 | SEALED STOPPER FOR AN OPENING IN A TUBING FOR JOINING A CHAMBER AND A PIPING, PARTICULARLY IN THE STEAM GENERATOR OF A NUCLEAR PRESSURISED WATER REACTOR - A sealed stopper for an opening in a tubing for joining a chamber and a piping including a fastening ring is provided. The stopper includes a rigid bearing plate and a sealing member carried by the bearing plate, and includes a seal having a planar and flexible central portion with a reduced thickness extending below the bearing plate and a peripheral portion radially deformable by a central expander of the peripheral portion against the inner surface of the fastening ring. | 11-08-2012 |
20120263266 | METHOD AND DEVICE FOR DETECTING THE DROP OF A CLUSTER IN A NUCLEAR REACTOR - The present invention relates to a method for detecting the drop of a cluster in a pressurized-water nuclear reactor, comprising the steps of: detecting a negative time derivative of the neutron flux, and comparing the absolute value of said time derivative to a first threshold value (S | 10-18-2012 |
20120243652 | BWR NUCLEAR FUEL ASSEMBLY WITH NON-RETAINED PARTIAL LENGTH FUEL RODS - A nuclear fuel assembly for a boiling water reactor is provided. The nuclear fuel assembly includes a base, a head and a bundle of full length fuel rods and partial length fuel rods. The bundle extends longitudinally between the base and the head, at least one partial length fuel rod having a lower end received in a housing provided in the base and delimited by a closed bottom larger than the lower end. The housing is further delimited by a peripheral wall surrounding the lower end and the partial length fuel rod rests freely on the bottom. | 09-27-2012 |
20120213320 | DEVICE FOR ASSISTING IN THE UNDERWATER EXTRACTION OR INSERTION OF AN ELONGATE ELEMENT DISPOSED IN A PIPE, AND METHOD FOR ASSISTING IN THE EXTRACTION OR INSERTION OF ONE SUCH ELEMENT - A device for assisting in the underwater extraction or insertion of an elongate element disposed in a pipe is provided. The device includes a clamping and vibration-generating assembly including a sealed housing bearing a gripper and including a member for tightening the gripper on the pipe, an adjustable vibrator for vibrating the housing and the gripper, and a member for measuring the vibration produced by the vibrator on the pipe in order to determine the optimum vibration The device also includes a controller for remotely controlling the gripper and the vibrator. A method for assisting in the extraction or insertion of an elongate element is also provided. | 08-23-2012 |
20120189089 | METHOD OF OPERATING A PRESSURIZED-WATER NUCLEAR REACTOR ALLOWING SAME TO PASS FROM A PLUTONIUM-EQUILIBRIUM CYCLE TO A URANIUM- EQUILIBRIUM CYCLE AND CORRESPONDING NUCLEAR FUEL ASSEMBLY - A method is provided for operating a nuclear reactor. The method includes operating the nuclear reactor for at least one plutonium equilibrium cycle during which the core contains plutonium-equilibrium nuclear fuel assemblies; subsequently, operating the reactor for transition cycles, at least some of the plutonium-equilibrium nuclear fuel assemblies being progressively replaced with transition nuclear fuel assemblies and then with uranium-equilibrium nuclear fuel assemblies; and then operating the nuclear reactor for at least one uranium equilibrium cycle. | 07-26-2012 |
20120163525 | METHOD OF OPERATING A PRESSURIZED-WATER NUCLEAR REACTOR FOR REACHING A PLUTONIUM EQUILIBRIUM CYCLE - A method is provided for operating a nuclear reactor. The method includes operating the nuclear reactor for an initial cycle during which a core contains initial nuclear fuel assemblies; then operating the nuclear reactor for transition cycles, at least some of the initial nuclear fuel assemblies being progressively replaced, during the replacement steps preceding the transition cycles, with transition nuclear fuel assemblies or with plutonium-equilibrium nuclear fuel assemblies; and then operating the nuclear reactor for at least one plutonium equilibrium cycle during which the core contains only plutonium-equilibrium nuclear fuel assemblies. | 06-28-2012 |
20120103995 | SEALED STOPPER FOR AN OPENING IN A JUNCTION TUBING BETWEEN A HOUSING AND A PIPE, AND METHOD FOR IMPLEMENTING SAID STOPPER - A sealed stopper for an opening in a junction tubing between an enclosure and a pipe, including an attachment ring. The stopper includes a rigid lid and a sealing assembly borne by the lid including a passive annular gasket including at least one annular internal chamber, a first static annular gasket, a second static annular gasket and a flat gasket ensuring the seal of the opening of the tubing. | 05-03-2012 |
20120090822 | METHOD FOR MANUFACTURING A BUNDLE OF PLATES FOR A HEAT EXCHANGER - A method is provided for manufacturing a bundle of plates for a heat exchanger made up of a stack of plates. The method includes reducing by machining the initial thickness of each plate by making at least at the periphery of the plate, at least one connecting shoe having a height greater than the thickness of the machined plate, forming on the central portion of the plate, corrugations, to be superposed pairwise on the plates, connecting the shoes in contact with the plates of each pair through a weld bead, superposing the pairs of plates and connecting the shoes in contact with the pairs of plates through a sealed weld bead by arranging a superposition of open or closed ends for alternate inflow or outflow of said fluid. | 04-19-2012 |
20120036933 | METHOD FOR THE NON-DESTRUCTIVE AND CONTACTLESS CHARACTERIZATION OF A SUBSTANTIALLY SPHERICAL MULTILAYERED STRUCTURE AND RELATED DEVICE - A method is provided for the non-destructive and contactless characterization of a multilayered structure having a substantially spherical shape and including at least two layers, separated by interfaces. The method includes using a laser for locally heating the structure in a thermoelastic state so that the structure is vibrated in a non-destructive manner, measuring the resonance frequencies of the vibration modes of the structure and deriving at least one characteristic concerning the integrity or the shape or the mechanical behavior of the structure from the resonance frequencies of the structure. | 02-16-2012 |
20120002775 | ASSEMBLY AND METHOD FOR DETECTING AND MEASURING THE FOULING RATEOF FLOW HOLES IN A SECONDARY CIRCUIT OF A PRESSURIZED WATER NUCLEAR REACTOR - An assembly for detecting and measuring the fouling rate by deposits containing at least one ferromagnetic material, including a probe which can be continuously moved inside a tube and which has a body carrying on its outer surface at least one magnetized source for self-orientation of the body of the, at least three magnetic field emitters and at least three magnetic field detectors each positioned between two contiguous emitters. | 01-05-2012 |
20110309077 | SEALING ELEMENT FASTENING SYSTEM FOR A PRESSURE VESSEL, IN PARTICULAR A REACTOR PRESSURE VESSEL - The invention relates to a sealing element fastening system for at least one sealing element of a pressure vessel, which has at least one opening and a sealing part, in particular a cover, provided for the opening. In the operating state of the pressure vessel each sealing element is at least partially inserted in an accommodating groove in the sealing part and corresponding sealing element fastening devices are positioned in each case in an indentation in the sealing part. The indentations are in each case sealed by a fill element in the operating state of the pressure vessel. | 12-22-2011 |
20110293058 | METHOD FOR MEASURING THE NEUTRON FLUX IN THE CORE OF A NUCLEAR REACTOR USING A COBALT DETECTOR AND ASSOCIATED DEVICE - A method for measuring the neutron flux in the core of a nuclear reactor, the method including several steps recurrently performed at instants separated by a period, the method comprising at each given instant the following steps: acquiring a total signal by a cobalt neutron detector placed inside the core of the reactor; assessing a calibration factor representative of the delayed component of the total signal due to the presence of cobalt 60 in the neutron detector; assessing a corrected signal representative of the neutron flux at the detector from the total signal and from the calibration factor; assessing a slope representative of the time-dependent change of the calibration factor between the preceding instant and the given instant; the calibration factor at the given instant being assessed as a function of the calibration factor assessed at the preceding instant, of the slope, and of the time period separating the given instant from the preceding instant. | 12-01-2011 |
20110280361 | LOWER NOZZLE FOR NUCLEAR FUEL ASSEMBLY FOR PRESSURIZED WATER REACTOR - A lower nozzle an upper end and a lower end for the lower nozzle to rest on a lower core plate of a reactor core and a lateral surface extending along a longitudinal axis from the lower end to the upper end. | 11-17-2011 |
20110268240 | DEBRIS FILTER FOR USE IN A NUCLEAR FUEL ASSEMBLY - A filter including a plurality of flow ducts extending in a longitudinal direction and each delimited between one pair of walls. | 11-03-2011 |
20110261920 | CONNECTING DEVICE FOR CONNECTING A GUIDE TUBE TO A LOWER END NOZZLE IN A NUCLEAR FUEL ASSEMBLY - A connecting device including a nut, a screw, a body having a bore for screwing the screw to the nut through the bore with the screw abutting an abutment surface of the body, a screw locking device for preventing loosening of the screw. | 10-27-2011 |
20110209547 | DEVICE AND METHOD FOR THE ULTRASOUND MONITORING, MEASURING AND TRACKING OF HEAT-SEALED SEAM BETWEEN TWO METAL PARTS - A device for checking, measuring and monitoring by ultrasound a hot weld seam between two metal parts, of the type including at least one ultrasonic transmitter. The device includes a shoe equipped with a planar face which is suitable for being in contact with a wall of one of the two parts and includes a housing for maintaining the ultrasonic transmitter in a predetermined orientation in relation to the wall, a cooling system for cooling the ultrasonic transmitter to a temperature below its operating temperature limit, and distributor for depositing and distributing a coupling product between the base plate of the ultrasonic transmitter and the wall. | 09-01-2011 |
20110187139 | HANDLING SYSTEM FOR A CONTAINER FOR NUCLEAR FUEL ASSEMBLY - A handling system including a tool for lifting the container, wherein the lifting tool includes a lifting carrier to be suspended and a member for gripping the container comprising removable devices for fastening the container onto the gripping member. | 08-04-2011 |
20110182393 | METHOD OF EVALUATING QUANTITIES RELATING TO THE DISTORTION OF A NUCLEAR FUEL ASSEMBLY - A method of evaluating at least one quantity relating to the distortion of a nuclear fuel assembly, the method including the following steps: the nuclear fuel assembly is placed in a volume of water bounded by an upper free surface; a camera is placed outside the volume of water, above the free surface; at least one image of at least one lateral face of the nuclear fuel assembly is taken; the at least one image is analyzed graphically and the at least one quantity relating to the distortion of the nuclear fuel assembly is deduced therefrom. | 07-28-2011 |
20110176650 | NUCLEAR REACTOR GREEN AND SINTERED FUEL PELLETS, CORRESPONDING FUEL ROD AND FUEL ASSEMBLY - A sintered fuel pellet for a water nuclear reactor fuel rod including a peripheral wall extending along a central axis and two end faces. At least one of the end faces includes at least a first chamfer extending from the peripheral wall towards the central axis with a first non-zero slope with respect to a plane perpendicular to the central axis and a second chamfer extending from the first chamfer towards the central axis with a second non-zero slope with respect to a plane perpendicular to the central axis, wherein the first slope is different from the second slope. | 07-21-2011 |
20110158373 | Nuclear Fuel Assembly Bottom Nozzle - A nuclear fuel assembly bottom nozzle, of the type including a perforated plate to allow water to pass through it, the nozzle having lateral faces, and at least one anti-debris element positioned on a lateral face to block out debris likely to infiltrate between the bottom nozzle and another adjacent bottom nozzle, characterized in that, in the free state, the or each anti-debris element permanently projects from the lateral face on which it is positioned, the or each anti-debris element being elastically deformable so as to retract towards the lateral face in the event of a force being exerted on the anti-debris element towards the lateral face. | 06-30-2011 |
20110129051 | Nuclear Fuel Assembly For Boiling Water Reactor - An assembly of the type having a water channel extending along a longitudinal axis and having an upper section of larger cross-section area than a lower section and at least one fuel rod receiving groove extending longitudinally on the outer surface of the lower section, fuel rods extending longitudinally and disposed around the water channel and fixing members for fixing at least one fuel rod to the water channel in the at least one groove below the upper section. | 06-02-2011 |
20110116588 | Method for Securing and Confining the Gasket Plane of a Vessel of a Nuclear Reactor and a Gasket for Applying this Method - A method including placing around the shoulder of the lid a ring-shaped gasket formed by a metal strip maintained on the vertical wall of the shoulder by self-maintaining members firmly attached to the strip, placing the lid bearing the ring-shaped gasket above the vessel by positioning it at a determined height, carrying out a cleanliness inspection of the gasket plane, lowering and laying the lid on the vessel so that the end side edges of the strip will come into contact with a horizontal wall of the lid and of the vessel flange respectively and attaching this lid on the vessel. | 05-19-2011 |
20110075789 | Module for Forming a Nuclear Fuel Assembly and Corresponding Nuclear Fuel Assembly - A module including a casing extending in a longitudinal direction, a bundle of fuel rods encased in and supported by the casing and connector provided on the casing for connecting the casing side-by-side to the casing of at least one other module to obtain a nuclear fuel assembly having a channel box defined by the casings of the assembled modules and of larger cross-section than the casing of each of the assembled modules and a bundle of fuel rods of larger cross-section than that of each the assembled modules. | 03-31-2011 |
20110046932 | Computer Implemented Method for Modelizing a Nuclear Reactor Core and a Corresponding Computer Program Product - A computer implemented method for modelizing a nuclear reactor core, includes the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated. | 02-24-2011 |
20110046931 | Computer Implemeneted Method for Modelizing a Nuclear Reactor Core and a Corresponding Computer Program Product - A computer implemented method for modelizing a nuclear reactor core, including the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated. The neutrons are sorted in a plurality of neutron energy groups, and the iterative solving procedure includes a multi-level V-cycle with a top level fed with the eigensystem for the plurality of neutron energy groups and at least one bottom level. | 02-24-2011 |
20110046930 | Computer Implemented Method for Modelizing A Nuclear Reactor Core and a Corresponding Computer Program Product - A computer implemented method for modelizing a nuclear reactor core, including the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated. | 02-24-2011 |
20110044422 | Computer Implemented Method for Modelizing a Nuclear Reactor Core and a Corresponding Computer Program Product - A computer implemented method for modelizing a nuclear reactor core, including the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, calculating neutron flux by using an iterative solving procedure of at least one eigensystem, the components of an iterant of the eigensystem corresponding either to a neutron flux, to a neutron outcurrent or to a neutron incurrent, for a respective cube to be calculated. | 02-24-2011 |
20110040530 | METHOD FOR INSTALLING INDUSTRIAL COMPONENTS IN AN ENVIRONMENT - A method for installing industrial components in an environment is provided, in which, with the aid of a computer-assisted design model representing the theoretical layout of the industrial components in the environment, various measuring points of the theoretical positioning of the supports of each component are determined, those theoretical measuring points are codified with values, parameterisable model measuring ranges are paramaterised by the codified values, and at least one measuring device is controlled with the aid of the codified values by application of the corresponding range in order to compare the actual positioning points in the environment as a function of theoretical positioning points of the supports of each component. The method is applicable to the installation of the components of the loops of the primary circuits of nuclear power stations. | 02-17-2011 |
20110029294 | Computer Implemented Method for Modelizing a Nuclear Reactor Core and a Corresponding Computer Program Product - The method comprises the steps of: partitioning the core in cubes to constitute nodes of a grid for computer implemented calculation, splitting the cubes into a first category and a second category, each cube of the first category being adjacent only to cubes from the second category so that the first category and second category of cubes constitute a checkerboard-like pattern, ordering the cubes of the first category and then the cubes of the second category, calculating neutron flux and/or thermohydraulics parameters by using an iterative solving procedure of at least one linear system and/or an eigensystem, the components of an iterant of the linear system and/or the eigensystem constituting the neutron flux and/or thermohydraulics parameters to be calculated, wherein, during the iterative solving procedure, calculations are conducted on the cubes of the first category then on the cubes of the second category. | 02-03-2011 |
20110004417 | METHOD FOR ESTIMATING THE CONCENTRATION OF A CHEMICAL ELEMENT IN THE PRIMARY COOLANT OF A NUCLEAR REACTOR - The invention comprises a process for estimating the concentration (C) of a chemical element in the primary coolant of a nuclear reactor, the reactor comprising means for injecting a dilution solution or a concentrated solution of the said chemical element in a predetermined concentration (C*) into the primary coolant and a sensor capable of measuring a quantity (C | 01-06-2011 |
20100297921 | ORBITAL APPARATUS FOR MACHINING A REVOLUTION METALLIC WALL - The invention relates to an orbital apparatus ( | 11-25-2010 |
20100284778 | Transport Container for Nuclear Fuel Assembly and Method of Transporting a Nuclear Fuel Assembly - A container for a non-irradiated nuclear fuel assembly including a single casing for receiving at least one nuclear fuel assembly, the casing being formed from an elongate tubular shell, the shell including a metallic internal layer delimiting at least one individual housing for receiving a nuclear fuel assembly, and a metallic external layer surrounding the internal layer, the shell being filled between its internal layer and its external layer, and from lids for closing the or each housing at the longitudinal ends of the shell. | 11-11-2010 |
20100269960 | METHOD FOR SURFACE PROCESSING A ZIRCONIUM OR HAFNIUM ALLOY, AND COMPONENT PROCESSED IN THIS MANNER - A method for surface processing at least a portion of a component of zirconium or hafnium alloy, including at least one operation of nanostructuring a surface layer of the alloy so as to confer on the alloy over a thickness of at least 5 μm a grain size which is less than or equal to 100 nm, the nanostructuring being carried out at a temperature which is less than or equal to that of the last thermal processing operation to which the component was previously subjected during its production. | 10-28-2010 |
20100260300 | Method of Determining the Value of a Parameter Representative of the Operability of a Nuclear Reactor, Determining System, Computer Program and Corresponding Medium - A method involving periodic implementation, during the same operating cycle of the reactor, the method including following steps of: a) calculating, from measurements provided by sensors present in the reactor, the three-dimensional distribution of the local power in the core, b) simulating at least one accidental transient occurrence of power applied to the calculated three-dimensional distribution of local power, c) identifying, using thermomechanical calculations, at least one rod which is the most likely to be subject to a fracture of the cladding thereof during the simulated transient occurrence of power, and d) determining, using thermomechanical calculations on the rod identified, the value of the parameter which is representative of the operability of the reactor. | 10-14-2010 |
20100246747 | NUCLEAR FUEL ROD SPACER GRID AND FRAMEWORK AND ASSEMBLY COMPRISING SUCH A GRID - A grid including at least two meshed grid parts intended to be superposed in a longitudinal direction, each grid part extending in a transverse plane, and the grid parts being moveable one relative to the other in at least one transverse direction between an open configuration for the insertion of nuclear fuel rods in the longitudinal direction through the grid parts, and a closed configuration allowing each fuel rod inserted through the grid parts to be clamped transversely between the grid parts. According to one aspect of the invention, the grid includes elements for transversely immobilizing the grid parts in the closed configuration, the immobilizing elements being designed to engage as the superposed grid parts are moved closer together in the longitudinal direction. | 09-30-2010 |
20100208858 | METHOD FOR SELECTING A LOADING MAP FOR A NUCLEAR REACTOR CORE, CORRESPONDING SELECTION SYSTEM, COMPUTER PROGRAM AND STORAGE MEDIIUM - A method for selecting a loading map for a nuclear reactor core including the following steps: a) providing production data relating to the nuclear fuel assemblies, b) providing neutron data which are representative of the operation of the core, c) calculating the three-dimensional distribution of the local power in the core, d) calculating the extreme value reached by at least one thermomechanical parameter within the nuclear fuel assemblies, and e) selecting, in accordance with the extreme values calculated, a loading map from the loading maps envisaged. | 08-19-2010 |
20100197484 | PREPARATION OF MINERAL PARTICLES IN A SUPERCRITICAL CO2 MEDIUM - The present invention relates to a process for preparing mineral particles (p) from mineral species precursors, said process comprising a step (E) in which a fluid medium (F) containing said precursors in solution and/or dispersed in a solvent is injected into a reactor containing CO | 08-05-2010 |
20100146759 | METHOD FOR REPAIRING GUIDE RAILS OF AN ASSEMBLY RADIALLY MAINTAINING A SUPPORT PLATE OF A PRESSURIZED WATER NUCLEAR REACTOR CORE - The invention concerns a method for repairing guide rails ( | 06-17-2010 |
20100126636 | ZIRCONIUM ALLOY RESISTANT TO CORROSION IN DROP SHADOWS FOR A FUEL ASSEMBLY COMPONENT FOR A BOILING WATER REACTOR, COMPONENT PRODUCED USING SAID ALLOY, FUEL ASSEMBLY, AND USE OF SAME - A zirconium alloy that is resistant to shadow corrosion for a boiling water nuclear reactor fuel assembly component, the alloy being characterized in that:
| 05-27-2010 |
20100116383 | METHOD OF HEAT TREATMENT FOR DESENSITIZING A NIKEL-BASED ALLOY RELATIVE TO ENVIRONMENTALLY-ASSISTED CRAKING, IN PARTICULAR FOR A NUCLEAR FOR A NUCLEAR REACTOR FUEL ASSEMBLY AND FOR A NUCLEAR REACTOR, AND A PART MADE OF THE ALLOY AND SUBJECTED TO THE TREATMENT - A heat treatment method for desensitizing a nickel-based alloy with respect to environmentally-assisted cracking, the alloy having the following composition in percentages by weight: C≦0.10%; Mn≦0.5%; Si≦0.5%; P≦0.015%; S≦0.015%; Ni≧40%; Cr=12%-40%; Co≦10%; Al≦5%; Mo=0.1%-15%; Ti≦5%; B≦0.01%; Cu≦5%; W=0.1%-15%; Nb=0-10%; Ta≦10%; the balance being Fe, and inevitable impurities that result from processing, characterized in that the alloy is held at 950° C.-1160° C. in an atmosphere of pure hydrogen or containing at least 100 ppm of hydrogen mixed with an inert gas. A part made of a nickel-based alloy having the composition and that has been subjected to the heat treatment. | 05-13-2010 |
20100111243 | FIXED CLUSTER HAVING A SPIDER-LIKE SUPPORT, CORRESPONDING PRESSURIZED WATER NUCLEAR REACTOR CORE AND ASSEMBLY COMPRISING A NUCLEAR FUEL ASSEMBLY AND SUCH A FIXED CLUSTER - A fixed cluster for the core of pressurized-water nuclear reactor including rods and a holder for rods. The holder includes: an upper head; fins extending radially towards the outside from the upper head; systems for mounting the rods and distributed on the fins; and at least two abutment elements on the upper plate of the core, each of the abutment elements protruding longitudinally from a respective fin beyond the mounting systems so as to be vertically oriented towards the top when the fixed cluster is provided on a nuclear fuel assembly. | 05-06-2010 |
20100108645 | DEVICE AND METHOD FOR AUTOMATIC UNDERWATER WELDING FOR MAKING A WELDING JOINT ON A SURFACE - The invention relates to a device for automatic under-water welding for making a welding joint ( | 05-06-2010 |
20100091932 | METHOD FOR DESIGNING A FUEL ASSEMBLY OPTIMIZED AS A FUNCTION OF THE STRESSES IN USE IN LIGHT-WATER NUCLEAR REACTORS, AND RESULTING FUEL ASSEMBLY - A method for design of a fuel assembly for nuclear reactors, including structural components made from zirconium alloy: the mean uniaxial tensile or compressive stress to which the components are subjected during the assembly life is calculated, the zirconium alloy of which the components are made is selected according to the following criteria: those components subjected to an axial or transverse compressive stress of between −10 et −20 MPa are made from an alloy with a content of Sn between Sn=(=0.025σ−0.25)% and Sn=−0.05σ%: those components subjected to such a stress of between 0 et −10 MPa are made from an alloy the Sn content of which is between Sn=traces and Sn=(0.05σ+1)%: those components subjected to such a stress of between 0 and +10 MPa are made from an alloy the Sn content of which is between Sn=0.05% and Sn=(0.07σ+1)%: and those components subjected to such a stress of between +10 and +20 MPa are made from an alloy the content of SN of which is between 0.05% and 1.70%. A fuel assembly made according to the method. | 04-15-2010 |
20100038062 | HEAT EXCHANGER ASSEMBLY, IN PARTICULAR FOR A HIGH-TEMPERATURE NUCLEAR REACTOR - The invention relates to an assembly for exchanging heat between first and second fluids, the assembly comprising a central manifold communicating with one of the inlet and the outlet for the first fluid; an annular manifold disposed around the central manifold and communicating with the other one of the inlet and the outlet for the first fluid; a plurality of heat exchangers interposed radially interposed between the central manifold and the annular manifold; and a plurality of axial inlet manifolds communicating with the inlet for the second fluid, and a plurality of axial outlet manifolds communicating with the outlet for the second fluid, the axial inlet and outlet manifolds being interposed circumferentially between the heat exchangers. According to the invention, the assembly has an inlet chamber disposed at a first axial end of the heat exchangers and putting the inlet(s) for the second fluid into communication with at least a plurality of axial inlet manifolds. | 02-18-2010 |
20100026325 | METHOD AND DEVICE FOR DETECTING STRUCTURAL ABNORMALITIES IN A SPHERICAL PARTICLE, PARTICULARLY IN A NUCLEAR FUEL PARTICLE FOR HIGH TEMPERATURE OR VERY HIGH TEMPERATURE REACTORS - The method for detecting at least one structural defect in a spherical particle ( | 02-04-2010 |
20100025380 | WELDING TORCH INCLUDING A CONVEX OPEN-WORK GRID FOR ENLARGING THE JET OF GAS - The invention relates to a welding torch comprising a torch body that is elongate along a longitudinal direction and that presents a working end, an electrode having a portion that projects longitudinally from the working end, and a channel for a flow of protective gas formed inside the body and terminating at the working end via at least one opening for ejecting gas in the form of a jet towards the projecting portion of the electrode. According to the invention, the torch includes jet-enlarger means for enlarging the jet of gas, which jet-enlarger means are in the form of a convex open-work grid covering the gas ejection opening(s). | 02-04-2010 |
20100014623 | TRANSPORT CONTAINER FOR NUCLEAR FUEL ASSEMBLIES AND USE OF SAID CONTAINER - A container including a support having at least one first longitudinal support surface defining a longitudinal housing for receiving a nuclear fuel assembly, and a door having a second longitudinal support surface. The door is movable between a position of holding the nuclear fuel assembly between the two longitudinal surfaces and a released position in which the assembly is free with respect to the support. The container includes means for adjusting the transversal separation between the first and second surfaces in the holding position of the door. | 01-21-2010 |
20100002825 | AUTOMATIC CONNECTION DEVICE AND METHOD FOR REMOTELY CONNECTING THE DUCTS FOR GUIDING A THERMOCOUPLE FOR THE UPPER INTERNALS OF A NUCLEAR REACTOR - The invention relates to a device for connecting the upper ( | 01-07-2010 |
20090310745 | NON-DESTRUCTIVE CHARACTERIZATION METHOD, ESPECIALLY FOR CHARACTERIZING PARTICLES OF NUCLEAR FUEL FOR A HIGH-TEMPERATURE REACTOR - The aim of the method is to characterize an element ( | 12-17-2009 |
20090296876 | SPACER GRID WITH SADDLE-SHAPED SUPPORTS AND CORRESPONDING NUCLEAR FUEL ASSEMBLY - A spacer grid for a nuclear fuel assembly for a light water reactor delimits a substantially regular array of cells housing nuclear fuel rods. | 12-03-2009 |
20090213979 | NUCLEAR POWER STATION COMPRISING AT LEAST ONE HIGH TEMPERATURE REACTOR - The invention relates to a nuclear power station comprising:
| 08-27-2009 |
20090174397 | INTERNAL INSTRUMENTATION SYSTEM FOR A NUCLEAR REACTOR, THE SYSTEM HAVING AN ADVANCED ELECTRONIC CARD, AND A CORRESPONDING METHOD OF MODIFYING AN INTERNAL INSTRUMENTATION SYSTEM OF A NUCLEAR REACTOR - This internal instrumentation system ( | 07-09-2009 |
20090141965 | Method and Device for Displaying and Monitoring the Profile of a Weld Bead Inside a Groove Provided Between Two Metal Workpieces - The invention relates to a method of displaying and monitoring the profile of a weld bead ( | 06-04-2009 |
20090141848 | NUCLEAR REACTOR PRIMARY CIRCUIT - The invention relates to a nuclear reactor primary circuit comprising a primary pipeline ( | 06-04-2009 |
20090122948 | Method of Determining at Least One Technological Uncertainty Factor for Nuclear Fuel Elements, and Corresponding Methods of Designing, Fabricating, and Inspecting Nuclear Fuel Elements - The invention relates to a method of determining at least one technological uncertainty factor in respect of nuclear fuel elements ( | 05-14-2009 |
20090119921 | Method for making orifices in the secondary casings of a pressurized water reactor steam generator - The method consists in making sure that the steam generator ( | 05-14-2009 |
20090060110 | Device and method for shutting off an orifice of a bundle wrapper of a steam generator of a pressurized-water nuclear reactor - The invention relates to a device ( | 03-05-2009 |
20090050295 | HEAT EXCHANGE ASSEMBLY EXCHANGING HEAT BETWEEN A FIRST AND A SECOND FLUID - The heat exchange assembly ( | 02-26-2009 |
20080310578 | Pressurizer Heater for the Primary Cooling System of a Pressurized-Water Nuclear Reactor - The invention relates to a heating rod for a pressurizer of a primary cooling system of a pressurized-water nuclear reactor, the rod comprising a metal outer shell ( | 12-18-2008 |
20080231855 | Method for Measuring the Anisotropy in an Element Comprising at Least One Fissile Material and a Corresponding Installation - This method comprises the steps of transmitting a beam of light onto a surface ( | 09-25-2008 |
20080219396 | Nuclear power plant using nanoparticles in closed circuits of emergency systems and related method - A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form to improve heat transfer and reduce corrosion is provided. The nanoparticles are delivered to a closed cooling circuit such as a CCWS. Methods for providing the nanoparticles are also provided. | 09-11-2008 |
20080219395 | Nuclear power plant using nanoparticles in emergency situations and related method - A nuclear power plant provides for delivery of nanoparticles to coolant found in the containment, for example during severe accident scenarios. The nanoparticles advantageously can be delivered passively or actively independently of any emergency core cooling system. The nanoparticle supply can include for example tanks storing nanofluids or solid nanoparticles, or dissolvable paints containing nanoparticles. Methods for providing the nanoparticles are also provided. | 09-11-2008 |
20080212733 | Nuclear power plant using nanoparticles in emergency systems and related method - A nuclear power plant with an improved cooling system using nanoparticles in solid or fluid form is provided. The nanoparticles are delivered in locations such as the cold leg accumulator and high and low pressure pumps of an emergency core cooling system. Motor driven valves and pressurization can aid in the delivery. Methods for providing the nanoparticles are also provided. | 09-04-2008 |
20080212072 | Photothermal Test Camera Provided With An Optical Device For Extending A Laser Beam Section - The inventive photothermal test camera ( | 09-04-2008 |