AREVA NP Inc. Patent applications |
Patent application number | Title | Published |
20150131768 | NUCLEAR FUEL ROD CLADDING INCLUDING A METAL NANOMATERIAL LAYER - A nuclear fuel cladding is provided. The nuclear fuel cladding includes a base cladding; and at least one nanomaterial layer deposited on a surface of the base cladding, the nanomaterial layer having an average grain size of between 5 to 400 nanometers. A method of manufacturing nuclear fuel cladding is also provided. The method includes depositing nanoparticles on a base cladding to form at least one nanomaterial layer, the nanoparticles having an average grain size of between 5 to 400 nanometers. | 05-14-2015 |
20150092901 | OPERATING A NUCLEAR REACTOR USING A DEPOSIT MODEL OF A NUCLEAR REACTOR HEAT TRANSFER SURFACE - A method of operating a nuclear reactor is provided. The method includes defining a layer increment of a deposit layer modeling a deposit on a heat transfer surface of the nuclear reactor; periodically updating a thickness of the deposit layer by adding the layer increment to the deposit layer; recalculating properties of the deposit layer after each layer increment is added to the deposit layer; determining a temperature related variable of the heat transfer surface as a function of the recalculated properties of the deposit layer; and altering operation of the nuclear reactor when the temperature related variable of the heat transfer surface reaches a predetermined value. A method of modeling a deposit on a heat transfer surface of a nuclear reactor is also provided. | 04-02-2015 |
20140211903 | METHOD OF OPERATING A POWER GENERATOR BASED ON NOBLE METAL INDUCED OXIDATION OF A HEAT TRANSFER SURFACE - A method of operating a power generator is provided. The method includes determining an amount of oxides on a heat transfer surface of the power generator as a function of a concentration of a noble metal substance in the oxides; and altering operation of the power generator when the amount of oxides on the heat transfer surface reaches a predetermined value. A method of operating a nuclear reactor is also provided. | 07-31-2014 |
20140184750 | Stereo Vision Encoded Ultrasonic Inspection - This invention applies optical tracking technology with an ultrasound inspection system to associate recorded position data with the inspection data. The reference targets of the optical tracking system can be attached to the inspection assembly to allow fully recorded position information to be associated with the ultrasonic, eddy current, or other nondestructive examination data without substantially impacting the overall envelope of the NDE inspection equipment. Moreover, the optical tracking system can be used to monitor skew or twist of the inspection equipment with respect to the normal rectilinear transducer orientation. The inspection equipment position information is then coupled to the inspection data to provide outputs equivalent to fully encoded multi-axis manipulator automated scans, but with less setup burden and equipment expense. | 07-03-2014 |
20140183341 | Optical Encoded Nondestructive Inspection - This invention applies optical sensing technology with an ultrasound inspection system to associate encoded position data with the inspection data. The compact electronics of the optical system can be attached to the inspection assembly to allow fully encoded position information to be associated with the ultrasonic, eddy current, or other nondestructive examination data without substantially impacting the overall envelope of the NDE inspection equipment. Moreover, because of the small size, the optical system can be used in tandem to monitor skew or twist of the inspection equipment with respect to the normal rectilinear transducer orientation. The inspection equipment position information is then coupled to the inspection data to provide data outputs equivalent to fully encoded multi-axis manipulator automated scans, but with less setup burden and equipment expense. | 07-03-2014 |
20140079468 | Jet Pump Stabilizer - A jet pump stabilizer is disclosed and claimed. The stabilizer includes a clamp body that is affixed about the riser pipe. Two U-clamps are connected to the clamp body, each U-clamp positioned about a jet pump mixer section. A wedge assembly is positioned between the clamp body and each mixer pipe, cooperating with the clamp body and U-clamps to laterally restrain the mixer sections. A clamp ring is positioned about each mixer section and retained in place by the U-clamps, wedge assemblies, and clamp body. A sealing ring is moveably connected to the clamp ring such that it is biased toward engagement with the jet pump diffuser. Seals provided on the stabilizer engage the jet pump assembly above and below the slip joint, preventing vibration-inducing leakage through the slip joint. | 03-20-2014 |
20140059787 | ELECTRICAL GENERATOR PARALLEL RING RESIN REMOVAL TOOLING - A resin removal tooling system for electric generator parallel rings including: a non-rotating sheath; a shaft mounted in the non-rotating sheath; a cleaning ball attached to the shaft, the non-rotating sheath positioning the cleaning ball; a high speed motor coupled to the shaft for rotating the shaft; a variable power supply connected to the high speed motor; and a tachometer for measuring a rotational speed of the high speed motor and the cleaning ball. A process of cleaning resin out of an electrical generator parallel ring including the following steps: inserting a cleaning ball mounted on a shaft into the parallel ring; verifying a location of the cleaning ball; rotating the shaft; measuring a rotational speed of the cleaning ball with a tachometer; and removing resin with the cleaning ball. | 03-06-2014 |
20140058183 | Immobilization of Technetium by Electroless Plating - A process of incorporating technetium into an electroless deposit, forming an alloy that is extremely resistant to corrosion and reduces the mobility of technetium on a geologic time scale is disclosed and claimed. The process includes providing a liquid containing technetium, such as an aqueous waste stream generated during the used nuclear fuel reprocessing activities. The technetium is collected and concentrated, and provided into an electroless deposition bath. A substrate, such as suitably prepared zero valent iron or stainless steel, is introduced into the bath to initiate autocatalytic electroless deposition of the technetium onto the substrate due to the difference in electrochemical potential between the plating bath and ti metals in solution. This causes a layer of technetium metal to form on the substrate. The electroless deposition is continued until virtually all of the technetium has been removed from the bath, and then continues to build a layer of technetium-free material on the outermost surface of the substrate. One or more additional deposition steps may be performed to armor the plated substrate against leaching/corrosion in a nuclear waste disposal facility. | 02-27-2014 |
20140054005 | Viscous Damping Stabilizer - The inventive viscous damping tube stabilizer includes modules or capsules containing a viscous material. Adjacent capsules are linked end to end by a flexible cable, allowing the device o pass through curves such as the U-bend regions of steam generator tubes. The weight of the entire assembly will keep it essentially connected to the tube inner diameter such that any tube vibration is transmitted to the stabilizer. The viscous material may only partially fill the capsules such that even under small motion the material can slip and slide past each other, and/or bump into walls, each microscopically absorbing some of the tube energy. By creating multiple cells inside the capsule, the capsule then have good operating characteristics no matter to what angle the individual capsule is oriented as it rests on the full U-bend. The viscous material may completely fill the capsules, which also have a perforated member positioned therein. Relative movement of the capsule and disc causes the viscous material to pass through the perforations, providing damping resistance to the movement. | 02-27-2014 |
20130338940 | EDDY CURRENT METHOD FOR THE CHARACTERIZATION OF BROACHED TUBE SUPPORT PLATE BLOCKAGE - A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range. | 12-19-2013 |
20130289900 | Gap Measurement Tool and Method of Use - A process of collecting and manipulating data to measure the gap between structural components of a piece of equipment or a system is disclosed and claimed. The technique uses ultrasonic zero degree longitudinal waveforms to measure the gap. The technique subtracts the average of two adjacent waveforms from the waveform being processed to remove data from reflections from the components to reveal the reflections generated by the gap. | 10-31-2013 |
20130235967 | METHOD FOR RECYCLING NUCLEAR CONTROL RODS AND RECYCLED CONTROL ROD SECTION - A method for recycling AgInCd control rod absorber bar material from a used control rod from a nuclear power plant includes sectioning AgInCd absorber bar from a used control rod into a first section and a second section, the first section having a higher radioactivity than the second section; and recycling the material of the second section of the AgInCd absorber bar. | 09-12-2013 |
20120219103 | VIBRATION REDUCTION TECHNIQUES FOR JET PUMP SLIP JOINTS - A method for retrofitting a boiling water reactor is provided. The method includes removing a mixing chamber from a slip joint defined by a diffuser and the mixing chamber, the mixing chamber having an inner surface and a bottom edge directing flow to the diffuser such that a recirculation zone at an entrance to the slip joint creates a diverging effective path for the leakage flow entering the slip joint. The method also includes providing a new inner surface and new bottom edge, the new inner surface and the new bottom edge being reshaped to decrease the size of the recirculation zone. A jet pump is also provided. | 08-30-2012 |
20110235767 | INSPECTION TOOL FOR TOP GUIDES OF A BOILING WATER REACTOR - A tool for inspecting a cell formed by grid beams of a top guide structure in a nuclear reactor is provided. The tool includes a camera; a support structure coupled to the camera for contacting at least one of the grid beams to support the camera within the cell; and at least one actuator moving the camera with respect to the support structure and along one of the grid beams, the at least one actuator coupling the camera to the support structure. A method for inspecting a cell formed by grid beams of a top guide structure in a nuclear reactor is also provided. | 09-29-2011 |
20110120497 | CORROSION PRODUCT CHEMICAL DISSOLUTION PROCESS - A method for removing corrosion products from a system, the method including: adjusting the system temperature to between 115° F. to 212° F.; injecting a cleaning dissolution solvent into the system; injecting a gas into the system after the system is filled with the cleaning dissolution solvent; the gas mixing with the solvent in the system; draining the solvent from the system after a predetermined period of time of dissolution; injecting a passivation composition into the system; injecting a gas into the system, the gas mixing the passivation composition; draining the system of the composition after a predetermined period of time of passivation; rinsing the system with a low volume solution; and rinsing the system at with a full volume solution. | 05-26-2011 |
20110110837 | SEGMENTED REACTORS FOR CAPACITY AND ENRICHMENT CHANGES IN CONVERSION OF URANIUM HEXAFLUORIDE TO URANIUM DIOXIDE - A dry conversion reactor for converting uranium hexafluoride to uranium dioxide, the dry conversion reactor including a gas-phase reaction segment and a fluidized bed segment, wherein at least one of the gas-phase reaction segment and the fluidized bed segment is a replaceable segment. A method for operating a dry conversion reactor utilizing a uranium hexafluoride to uranium dioxide conversion process, the method including replacing at least one conversion reactor segment. | 05-12-2011 |
20110069804 | Jet Pump Slip Joint Modification for Vibration Reduction - A method for retrofitting a boiling water reactor slip joint of a jet pump to reduce vibrations is provided. The method includes removing a mixing chamber from an existing slip joint defined by a diffuser and the mixing chamber, the existing slip joint defining an existing annular gap, and providing a new slip joint defining a new annular gap, the new annular gap being reshaped to permit reduced vibration. A jet pump and a method of operating a jet pump are also provided. | 03-24-2011 |
20110022333 | EDDY CURRENT FOR THE CHARACTERIZATION OF BROACHED TUBE SUPPORT PLATE BLOCKAGE - A method for determining tube support plate blockage of a steam generator includes the following steps: measuring at least five different eddy current values per tube support intersection; calculating a nominal clean fit radius of flow hole; determining a center signal response; converting the center signal response to a deposit thickness; determine an edge reduction; converting the edge reduction to an edge thickness; calculating the resulting flow hole radius; verifying the reasonableness of the resulting flow hole radius; and determining a virtual calibration range. | 01-27-2011 |
20110019790 | ADVANCED FUEL CRUD SAMPLING TOOL METHOD - A method to perform an analysis of two types of CRUD on a nuclear fuel rod, including providing a nuclear fuel rod with a first and second layer of CRUD on an exterior of the fuel rod; brushing the first layer of CRUD from the fuel rod with a CRUD tool on a selected area; wherein the tool has a brushing device, a force applied to the brushing device on the fuel rod to remove the first layer of CRUD, the force being sufficient enough to perform such removal; collecting the first layer of CRUD from the brushing device, scraping the second layer of CRUD from the fuel rod in the selected area with the tool, wherein the tool has a scraping device and a second force is applied to the tool for scraping, collecting the second layer of CRUD from the scraping device, and analyzing the first layer and second layer of CRUD separately with a scanning electron microscope. | 01-27-2011 |
20100326474 | ELECTRICAL GENERATOR PARALLEL RING RESIN REMOVAL TOOLING - A resin removal tooling system for electric generator parallel rings including: a non-rotating sheath; a shaft mounted in the non-rotating sheath; a cleaning ball attached to the shaft, the non-rotating sheath positioning the cleaning ball; a high speed motor coupled to the shaft for rotating the shaft; a variable power supply connected to the high speed motor; and a tachometer for measuring a rotational speed of the high speed motor and the cleaning ball. A process of cleaning resin out of an electrical generator parallel ring including the following steps: inserting a cleaning ball mounted on a shaft into the parallel ring; verifying a location of the cleaning ball; rotating the shaft; measuring a rotational speed of the cleaning ball with a tachometer; and removing resin with the cleaning ball. | 12-30-2010 |
20100325859 | Method for Repairing Primary Nozzle Welds - A method for providing weld inlays and onlays to primary nozzles of a nuclear reactor comprising: providing a first welding device in a first primary nozzle of the nuclear reactor; providing a second welding device in a second primary nozzle of the nuclear reactor; providing a third welding device in a third primary nozzle of the nuclear reactor; and operating the first, second and third welding devices at the same time. Other methods are also provided. | 12-30-2010 |
20100243062 | POWER LINE DATA ACQUISITION - A motor operated valve diagnostic data acquisition system including: a motor operated valve assembly; a transmitter, the transmitter being permanently connected in a housing of a motor operated valve assembly; a receiver, the transmitter transmitting signals to the receiver via motor operated valve cables, the cables being existing motor operated valve cables; and electronic circuitry connected to the receiver, the electronic circuitry processing the signals received by the receiver. | 09-30-2010 |
20100242576 | UNDERWATER METHOD AND APPARATUS FOR DETECTING LEAKS IN A METALLIC TANK OR PIT LINER PLATE - A leak detecting apparatus for detecting flaws in a surface submerged in liquid is provided that includes a vacuum head for contacting the surface and forming a vacuum chamber filled with liquid between the surface and the vacuum head, the vacuum head including a multi-surface elastomer seal for contacting the surface; and a vacuum generator for pulling gas through a flaw in the surface into the vacuum head and to the gas separation chamber so as to displace the liquid from the gas separation chamber. A method for detecting flaws in a surface submerged in liquid is also provided. | 09-30-2010 |
20100186825 | PIPE ASSEMBLY WITH SCOOP FOR DIRECTING FLUID INTO A STANDPIPE AND FOR MITIGATING ACOUSTIC AND VORTEX COUPLED RESONANCE - A piping assembly for directing fluid and mitigating acoustic and vortex coupled resonance is provided that includes a main pipe delivering fluid in a first direction; a standpipe coupled to the main pipe at an intersection; and a scoop positioned at the intersection directing the fluid towards the standpipe. A scooping insert and a method for disrupting vortex shedding in a piping assembly are also provided. | 07-29-2010 |
20100119028 | Nuclear reactor steam dryer manipulator - A BWR steam dryer remote visual inspection system including a support moveable along a first axis over the steam dryer, the support having a longitudinal direction; a trolley movable along the support in the longitudinal direction; a mast fixed to the trolley and moveable at a predetermined angle with respect to a plane defined by the first axis and longitudinal direction; and a camera coupled to an end of the mast. | 05-13-2010 |
20100080335 | Boiling water reactor nuclear power plant with alcohol injection - A nuclear power plant is provided including a BWR, a reactor cooling system cooling the BWR, an HWC hydrogen injection system connected to the reactor cooling system and an alcohol injection system connected to the reactor cooling system. Methods for providing methanol and hydrogen are also provided. | 04-01-2010 |
20090238321 | Nuclear power plant with actinide burner reactor - A nuclear reactor includes a coolant and a core. The core includes a moderator material and a plurality of fuel assemblies arranged within the moderator material, each fuel assembly including an inner region and an outer region surrounding the inner region. The inner region includes at least one first fuel structure containing at least one byproduct actinide, and the outer region includes a plurality of second fuel structures containing thermal spectrum driver fuel, the second fuel structures being less than one thermal neutron mean free path apart. Other embodiments are also provided, as is a nuclear power plant and a fuel assembly. | 09-24-2009 |
20090183694 | System and method for crevice cleaning in steam generators - A method is provided for cleaning crevices between a plurality of tubes and a plurality of tube support plates supporting the tubes in a steam generator. The steps include filling a secondary side of the steam generator with a solvent to a first level above a first tube support plate to be cleaned, draining the solvent to a second level lower than the first tube support plate, and refilling the secondary side of the steam generator with the solvent to a third level above the first tube support plate. A cleaning system is also provided. | 07-23-2009 |
20090118560 | Nuclear waste removal system and method using wet oxidation - Methods for removing nuclear waste from a component are provided. In one embodiment, the method includes the steps of supplying oxalic acid to the nuclear waste on the component to form an oxalic acid/waste solution, feeding the oxalic acid/waste solution from the component, feeding an oxidant to the oxalic acid/waste solution to form carbon-dioxide, water and a precipitate, and separating the precipitate from the water. A system for removing nuclear waste is also provided. | 05-07-2009 |
20090086878 | Boiling water reactor nuclear power plant with alcohol injection - A nuclear power plant is provided including a BWR, a reactor cooling system cooling the BWR, an HWC hydrogen injection system connected to the reactor cooling system and an alcohol injection system connected to the reactor cooling system. Methods for providing methanol and hydrogen are also provided. | 04-02-2009 |