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7595087 Process of forming platinum coating catalyst layer in moisture-generating reactor  
A barrier film which has uniform thickness and excellent adhesiveness to the base material and superbly functions to protect a platinum film can be formed on the inner wall surface of a...
7542539 Apparatus and method for ultrasonically cleaning irradiated nuclear fuel assemblies  
An apparatus for cleaning an irradiated nuclear fuel assembly includes a housing adapted to engage a nuclear fuel assembly. A set of ultrasonic transducers is positioned on the housing to supply...
7472045 Method for perturbating a nuclear reactor core fuel bundle design to generate a group of designs  
A method has been developed to select fuel rod enrichments for a fuel bundle of a nuclear reactor, the method including: creating an ordered list of fuel rod types in an initial fuel bundle design;...
7449101 Method of reducing corrosion of metal material  
In a method of reducing corrosion of a metal material, a substance such as semiconductor for generating an electric current by thermal excitation is coated or adhered on a metal material surface,...
7389669 Mechanical stress improvement process  
A process for reducing residual tensile stresses in high nickel-chromium alloy nozzle safe-end welds of pressurized water reactor nuclear pressure vessels such as are found at the reactor vessel...
7346140 Reactor structural member and method of suppressing corrosion of the same  
A photocatalytic substance having the properties of an n-type semiconductor is deposited on a surface of a metal base made of a stainless steel or Inconel. When necessary, the hydrogen...
7280946 Method and arrangement for determining pin enrichments in fuel bundle of nuclear reactor  
A method and arrangement of determining pin enrichments for a fuel bundle of a nuclear reactor, where a plurality of input parameters and target conditions may be input and enrichment changes, to...
7264770 Mitigation of stress corrosion cracking of structural materials exposed to a high temperature water  
A method for mitigating stress corrosion cracking of a component exposed to a high temperature water in a high temperature water system is provided. The method comprises the steps of lowering...
7031779 Method and apparatus for automated crack behavior prediction determination  
A method of predicting component crack behavior in a nuclear reactor provides access to a crack growth behavior model over a global network. A user inputs water chemistry and material...
7027549 Nuclear power plant system and method of operating the same  
Migration of radioactive materials from a pressure vessel to a steam system in a nuclear power plant is suppressed by using a dryer ( 3 ) provided with corrugated plates ( 22 ) having surfaces...
7023949 Jet pump assembly repair method  
A BWR jet pump assembly has a wedge slidably mounted on a jet pump that is movable under the force of gravity to seat between a bracket and the jet pump in order to horizontally support the jet...
6968028 Nuclear power station having a gas-injection device for a coolant  
A nuclear power station includes a feedwater/steam circuit having a condensate-purification device and a feedwater pump connected upstream of a reactor pressure vessel. A branch line has a...
6937686 Iron control in BWR's with sacrificial electrodes  
Method for controlling the level of iron in feedwater of a BWR wherein an iron-containing sacrificial electrode in placed contact with the feed water dissolution of the electrode is induced at a...
6921515 Apparatus for chemical decontamination  
In a chemical decontamination apparatus, a catalyst decomposition column in an upstream side of an ion exchange resin column and a hydrogen peroxide injection apparatus in a further upstream side,...
6898259 Process for reducing the corrosion of a component of a nuclear facility, and component of a nuclear facility  
The corrosion of a component in a water-guiding loop of a nuclear facility is reduced. A protective layer is produced with a sol-gel process. Prior to the sol application, water that wettens the...
6891912 Fuel assemblies in a reactor core and method of designing and arranging same  
A reactor core ( 104 ) includes fuel assemblies ( 202 ) arranged in a loading pattern ( 1100 ) in response to corresponding power levels of the fuel assemblies ( 202 ). A crud deposition model (...
6885721 Inhibition method of stress corrosion cracking of nuclear steam generator tubes by lanthanum boride  
The present invention relates to a method for inhibiting stress corrosion cracking occurring on steam generator tubes in the secondary side of nuclear power plants and an inhibitor therefor. The...
6873672 Procedure and device for measuring resistance to hydriding of tubes and tubular claddings  
The method involves measuring hydrogen permeation in the tubes by mass spectrometry, wherein the tube is inserted into a high or ultrahigh vacuum device in which a mass spectrometer and a total...
6856665 Method for controlling water quality in nuclear reactor and nuclear power plant to which the method is applied  
A method for controlling water quality in a nuclear reactor comprises a first and second steps. The first step is to make an amount of iron, which is carried into the nuclear reactor and...
6810100 Method for treating power plant heater drain water  
Oxygen is mixed with heater drain water of power plant which contains fine particles of iron oxides such that the concentration of the dissolved oxygen in the heater drain water after the mixing of...
6793883 Application of catalytic nanoparticles to high temperature water systems to reduce stress corrosion cracking  
A method and system for reducing stress corrosion cracking in a hot water system, such as a nuclear reactor, by reducing the electrochemical corrosion potential of components exposed to high...
6714618 Temperature-based method for controlling the amount of metal applied to metal oxide surfaces to reduce corrosion and stress corrosion cracking  
Method for controlling the amount of metal atoms deposited into an oxide layer present on a metal surface, which metal atoms increase the corrosion resistance of metal when present in the oxide...
6654436 Stud enclosure and method of use  
A stud enclosure for protecting a stud extending upwardly from a nuclear reactor pressure vessel (RPV) flange has a cylindrical can with a capped end and an open end. The capped end has an axially...
6639962 Preventive maintenance method and apparatus of a structural member in a reactor pressure vessel  
A preventive maintenance method and apparatus for a structural member in a reactor pressure vessel according to the present invention reduce a tensile residual stress on a surface of the structural...
6636579 Device and method for repairing inside of reactor pressure vessel  
An opening portion 3 is produced by cutting a recirculating piping 72 connected to a recirculating nozzle 2 of a reactor pressure vessel 1. A repairing device is brought into an annulus 10...
6633623 Apparatus and methods for protecting a jet pump nozzle assembly and inlet-mixer  
A jet pump for a nuclear reactor includes a riser and an inlet mixer having a set of nozzles and a mixing section for receiving coolant flow from the nozzles and suction flow from an annular space...
6610185 Electrochemical corrosion potential sensor and method of making  
A sensor for measuring electrochemical corrosion potential, and a method for manufacturing a sensor, the sensor comprising a tubular ceramic probe having a closed tip at one end, the probe at least...
6606368 Method of operating nuclear power plant, nuclear power plant, and method of controlling water chemistry of nuclear power plant  
In a nuclear power plant, by injecting an amount of hydrogen small enough not to increase a radiation dose rate of the main steam system, ECP of metallic component materials composing a nuclear...
6556642 Inhibition method of the secondary side stress corrosion cracking in nuclear steam generator tubes  
The present invention relates to a method for inhibiting stress corrosion cracking occurring on steam generator tubes in the secondary side of nuclear power plants and an inhibitor therefor. The...
6549603 Method of chemical decontamination  
To suppress a decrease of thickness due to corrosion of structural members and to achieve a removal of radionuclides with good efficiency in a nuclear power plant, oxidation decontamination is...
6548178 Method of reducing corrosion potential and stress corrosion cracking susceptibility in nickel-base alloys  
A method for reducing in situ the electrochemical corrosion potential and susceptibility to stress corrosion cracking of a nickel-base alloy and boiling water nuclear reactor components formed...
6549602 Incore piping section maintenance system of reactor  
An incore piping section maintenance system of a reactor comprises a maintenance system main body which is fixed to a maintenance target portion in a reactor pressure vessel or in the vicinity...
6542566 Cladding for use in nuclear reactors having improved resistance to stress corrosion cracking and corrosion  
An improved fuel element for use in a nuclear reactor comprised of a central core of nuclear material, which is surrounded by a composite cladding. The cladding has an outer metallic tubular...
6512806 Component designed for use in a light water reactor, and a method for the manufacture of such a component  
A component ( 1 ) designed for use in a light water reactor and at least partly comprised by a metal and/or a metal alloy presents a coatings ( 4, 7 ) at its outer surface ( 3 ) and its inner...
6487265 Treatment method of nuclear reactor internal component  
Surfaces of the structural components of a nuclear power plant exposed to reactor water are wetted with an electroless plating solution containing an electrical insulating substance. The electrical...
6473480 Method and apparatus for maintaining proper noble metal loading for a noble metal application process for water-cooled nuclear reactors  
A non-steady state computer model of water in a Boiling Water Reactor (BWR) primary water flow circuit is used to represent the water chemistry and noble metal loading during, for example, an in...
6430249 Polymer dispersants and methods of use in a nuclear steam generator  
A novel high-purity polymer dispersant and sludge conditioner added to the feedwater entering the secondary side of a nuclear steam generator for minimizing the accumulation of metal-oxide deposits...
6415010 Catalytic hydrogen peroxide decomposer in water-cooled reactors  
A metal cooling tube of a water-cooled nuclear reactor, having an inner surface thereof exposed to an aqueous cooling medium containing hydrogen peroxide. The cooling tube has its inner surface...
6411667 Banded ECP sensor  
An ECP sensor includes a tubular ceramic probe having a closed tip at one end packed with a metal and metal oxide powder. A metal support tube receives an opposite end of the probe, and is joined...
6391173 Electrochemical corrosion potential sensor  
An electrochemical corrosion potential sensor includes a ceramic tip insulating member, and a sensor tip joined to the ceramic tip insulating member, the sensor tip comprising an alloy. Further, a...
6347130 Fuel assembly with short fuel units  
A fuel assembly for a boiling water reactor comprising a plurality of fuel units, stacked on top of each other, each of which comprising a plurality of fuel rods extending vertically between a top...
6314153 Process for introducing zinc into a water-containing component of the primary system of a nuclear power plant  
Disclosed is a process for introducing zinc into a water-containing component of the primary system of a nuclear power plant, in particular for preventing the deposition of radioactive cobalt...
6278756 Electrochemical corrosion potential sensor with increased lifetime  
The invention relates to a sensor for a measuring an electrochemical corrosion potential comprising a sensor tip, a conductor electrically connected to the sensor tip, an insulating member which...
6240155 Preventive maintenance apparatus for structural members in a nuclear pressure vessel  
A method of performing maintenance on a structural member inside a reactor pressure vessel includes lowering an annular guide rail having a second lug until the guide rail rests on an upper flange...
6226342 Fuel assembly comprising a component for retaining elongated elements  
A fuel assembly (1) comprising a plurality of elongated elements (3) filled with nuclear fuel and at least one component (5, 6, 7) for retaining the elongated elements (3), wherein the retaining...
6128361 Coating for reducing corrosion of zirconium-based alloys induced by . .beta-particle irradiation  
A technique for reducing the shadow corrosion effect in zirconium-based alloys caused by β-particles emitted by adjacent components containing one or more elements that emit β-particle flux when...
6099718 Method and device for checking and characteristics of a surface layer of a zirconium-alloy element and use for the checking of fuel rods for a nuclear reactor  
A sinusoidal voltage is appied to a zirconium alloy clad fuel rod. The current is measured and the impedance is determined to provide a check for the compactness and adhesion of an oxide surface...
6047241 Method of selective corrosion rate analysis for a fluid processing plant  
A method of selective corrosion rate analysis is shown for generating an inspection and replacement schedule for a fluid processing plant. The method includes the steps of identifying a system from...
6033493 Process for coating a passivatable metal or alloy substrate with an oxide layer, and fuel assembly cladding and guide tubes and spacer grid coated with an oxide layer  
6028906 Manufacturing method of control rod for boiling water reactor  
The present invention relates to a control rod installed in a boiling water reactor (BWR), and particularly to a control rod using metal. An object of the present invention is to provide a...
Matches 1 - 50 out of 210 1 2 3 4 5 >