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7616727 |
Methods of editing fuel bundle groups
A method of fuel bundle consideration in a reactor. The method includes creating or editing bundle groups including fuel bundles.
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7613272 |
Methods of using fuel bundle groups as evaluation constraints
A method of fuel bundle consideration in a reactor. The method includes creating or editing bundle groups including fuel bundles.
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7593501 |
Segment make-up system and method for manufacturing nuclear fuel rods
A method to insert nuclear fuel pellets into a fuel rod cladding tube, having the steps of providing a cladding tube, providing at least one nuclear fuel pellet to be incorporated into the cladding...
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7567645 |
Modular integrated head assembly
A two-part integrated head assembly ( 100 ) is disclosed wherein the lower portion ( 110 ) attaches to, and is supported by, the reactor vessel closure head ( 90 ), and the upper portion ( 160 ) is...
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7551705 |
Fuel assembly top nozzle repair sleeve and method for repairing a fuel assembly
A method and device to repair nuclear fuel assembly structural defects in the top nozzle to guide thimble connection, wherein the device includes a repair sleeve comprising tendons configured to...
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7539280 |
Nuclear fuel rod loading method and apparatus
A method to load a nuclear fuel rod, comprising, providing nuclear fuel pellets in a fuel plate transfer unit; transferring the nuclear fuel pellets from the fuel plate transfer unit to a fuel...
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7520043 |
Method of securing a tube in a bore through a spherical wall, and a device for depositing welding material in a facing
An annular facing is machined in an inside surface of the spherical wall around the periphery of a zone where the wall has a bore for securing the tube passing therethrough. A first welding...
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7512207 |
Apparatus for delivering a tool into a submerged bore
An apparatus for delivering a tool into a nuclear reactor jet pump submerged in a reactor pool includes a frame, and a propulsion unit for controlling the movement of the tool delivery apparatus...
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7505546 |
Method of preventing separation of feedwater sparger end bracket assemblies
A method of preventing separation of a feedwater sparger end bracket assembly comprises installing first and second clamp members of a clamp over a feedwater sparger end bracket assembly in...
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7499840 |
Method and apparatus for creating and editing a nuclear reactor core loading template
The apparatus for creating and editing a nuclear reactor core template includes a graphical user interface and a processor controlling the graphical user interface to display a graphical...
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7409032 |
Method of fuel bundle consideration in a reactor
A method of fuel bundle consideration in a reactor. The method includes creating or editing bundle groups including fuel bundles.
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7386087 |
Method and device for loading a fuel assembly into the core of a nuclear reactor
The invention relates to a method and a device for loading a fuel assembly into the core of a nuclear reactor. The inventive method consists in: inserting a dummy assembly ( 4 ) into the loading...
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7330525 |
Method and apparatus for maximizing radiation shielding during cask transfer procedures
A transfer cask for maximizing the radiation shielding for spent nuclear fuel during cask transfer procedures has a cylindrical inner shell forming a cavity within which a spent nuclear fuel...
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7289590 |
Method and apparatus for handling a tube guide of upper interval equipment of a nuclear reactor
A device for handling a guide tube assembly. The assembly has an upper tube and a lower tube in each of which there are fixed horizontal guide plates arranged such that they are spaced apart in an...
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7272204 |
Method and apparatus for clamping a riser brace assembly in nuclear reactor
An apparatus and method are provided which are designed to structurally replace welds that attach a riser brace assembly to a jet pump riser pipe. The riser brace assembly may include an upper...
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7206372 |
Methods of repairing leaking elongate hollow members in boiling water reactors
In a method for sealing a hollow, elongate member within a reactor pressure vessel of a nuclear reactor, a section of the elongate member may be removed to separate the elongate member into an...
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7155715 |
Distributed software system visualization
A data management system stores and visualizes data generated during process management. The data management system provides different data management services and definitions of these are stored...
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7145976 |
Procedure and means for replacing and procedure for repairing a section of a pipe in the primary circuit of a nuclear reactor
In a nuclear reactor, cooled by pressurized water, an apparatus is employed for replacing a section of a primary circuit primary pipe that interconnects first and second components of a primary...
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7139357 |
Reactor servicing platform
A method of servicing a nuclear reactor during a reactor outage is provided. The reactor includes a primary containment vessel and a reactor pressure vessel positioned in the primary containment...
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7139356 |
Procedure and means for replacing and procedure for repairing a section of a pipe in the primary circuit of a nuclear reactor
Marking of the cuts which have to be made, cutting of the section at two ends, removal of the section which has to be replaced, bevelling of the joint ends of the parts remaining after the section...
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7139358 |
Below grade cask transfer facility
A system and method for transferring a canister of spent nuclear fuel from a transfer cask to a receiving cask. In one aspect, the system comprises a below grade opening adapted for receiving a...
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7139359 |
Integrated head assembly for a nuclear reactor
An integrated head assembly ( 100 ) is disclosed for a nuclear reactor. The preferred integrated head assembly includes a lift assembly ( 150 ) that supports the reactor vessel closure head ( 90 )...
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7139353 |
Boiling water reactor nuclear fuel assembly lifting support
A lifting support for a boiling water reactor nuclear fuel assembly comprising a grappling head configured to allow attachment to a lifting device, a body with an upper end and a lower end, the...
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7120218 |
Method for calibrating steam generator water level measurement
A method is provided for determining and controlling feed water level in a steam generator of a nuclear power plant, whereby the water level sensor is calibrated in terms of the pressure drop...
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7076017 |
Apparatus and method for repairing reactor vessel cladding using a seal plate
A seal plate for repairing damaged areas in a pressure vessel cladding includes a first side and an opposing second side and a sealing portion located on the second side, with the sealing portion...
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7058154 |
Systems and methods for managing assets using an interactive database
The disclosed invention is a system and a method utilizing a web-based interactive database to automate the process for managing internal components of a plant. The system captures all essential...
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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...
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6990714 |
Modular submersible repairing system and repairing method
A modular submersible repairing system includes a working unit having a tool module capable of repairing structures in a reactor. A scanning/pitching module is capable of being selectively...
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6950489 |
Guide tube for an instrumentation lance extending into a pressure vessel, reactor pressure vessel, and a method for preventing the accumulation of particles outside the pressure vessel in a guide tube
The invention relates to a guide tube especially for an instrumentation lance extending into a reactor pressure vessel. The guide tube includes a lower tube section and an upper tube section that...
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6909765 |
Method of uprating an existing nuclear power plant
An improved method of increasing the power output of an existing nuclear power plant includes increasing the thermal power output of the plant's nuclear island and constructing of an auxiliary BOP...
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6895067 |
Smooth collet for pulling fuel rods
A method and apparatus is disclosed for smoothly inserting a fuel rod loader through the skeleton of a fuel cell and then for pulling an attached fuel rod into the fuel rod skeleton while keeping...
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6882696 |
Control rod for boiling water reactor and method for manufacturing the same
A tie rod having a cruciform cross section is provided with steps for fixing sheaths at tips of cruciform arms of the tie rod; the tips of each of sheaths are fitted onto the steps of the tie rod,...
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6876715 |
Measurement system of torsion vibration for reactor internal pump
Object of this invention is to provide an axial torsional vibration measurement device of the reactor internal pump capable of measuring the axial torsional vibration easily. The vibration detector...
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6865242 |
Method and device for restoring the fall-time of at least one control cluster for regulating reactivity in the core of a light-water-cooled nuclear reactor
After a nuclear reactor has been stopped and allowed to cool down following a period of operation, action is taken in a pool of the nuclear reactor on at least one guide tube of the activated upper...
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6862329 |
In-cycle shuffle
According to the method, a reactor core is shut down during the operation cycle. One or more fuel bundles of the reactor core are then moved to new positions within the reactor core to increase a...
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6856664 |
Reactor servicing platform
A modular reactor servicing platform for a nuclear reactor is provided. The modular servicing platform includes a plurality of modular sections coupled together, a support structure coupled to the...
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6856663 |
Reactor servicing platform
A reactor servicing platform for a nuclear reactor is provided. The nuclear reactor includes a reactor pressure vessel positioned in a primary containment and at least one refuel bridge. The...
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6834092 |
Method of repairing leaking elongate hollow members in boiling water reactors
The method facilitates sealing a control rod drive (CRD) housing to a stub tube in a reactor pressure vessel of a nuclear reactor, if any cracks develop proximate a heat affected zone of the stub...
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6811746 |
Zirconium alloy having excellent corrosion resistance and mechanical properties for nuclear fuel cladding tube
The present invention relates to a zirconium alloy having excellent corrosion resistance and mechanical properties and a method for preparing a nuclear fuel cladding tube by zirconium alloy. More...
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6809283 |
Noble metal in-situ sampling method and apparatus
An electric discharge machining sampling apparatus for obtaining samples from a surface of metal components provided. In an exemplary embodiment, the sampling apparatus is operable underwater and...
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6788756 |
Jet pump set screw wedge
A piping support wedge apparatus for a jet pump in a nuclear reactor is provided. In an exemplary embodiment, the wedge apparatus includes a first tapered wedge segment having a first end portion...
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6788755 |
Safe lift and process for transporting canisters of spent nuclear fuel
A system and method for moving a canister of spent nuclear fuel from a first location, which may be within a nuclear power generation facility to a second location such as a storage cask that is...
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6782070 |
Method of handling a large structure in a reactor building
When carrying the large structure out through an aperture portion provided at a roof of a reactor building, a chamber for covering the aperture is provided at the roof so that work of providing the...
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6773219 |
Control rod drive handling assembly for a nuclear reactor
A positioning apparatus for a CRD handling assembly for a nuclear reactor. The positioning apparatus includes at least one linear slide rail, a drive screw coupled to the at least one slide rail,...
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6754673 |
Method and system for assessing plant parameters and performance over a global network
Plant parameters and performance of an industrial plant such as a boiling water nuclear reactor plant can be assessed over a global network. Plant parameter and performance data are compiled from a...
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6744841 |
Method for carrying equipment out of nuclear power plant
A method of carrying equipment out of a nuclear reactor building that, in carrying equipment rendered radioactive out of a nuclear reactor building, makes it possible to shorten the operating time...
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6731715 |
Reactor vessel handling method
One of methods for carrying out a reactor vessel according to the present invention comprises the steps of removing an overhead traveling crane in a reactor containment vessel of a pressurized...
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6715201 |
Modular submersible repairing system
A modular submersible repairing system includes a working unit having a tool module capable of repairing structures in a reactor. A scanning/pitching module is capable of being selectively...
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6718002 |
Method and device for removing radioactive deposits
A device and method for removing radioactive crud material deposited on surfaces of a nuclear fuel assembly in a nuclear plant is provided. The device comprises a container arranged to accommodate...
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6704386 |
Fuel channel box and a method of manufacturing the same
A fuel channel box manufacturing method processes a fuel channel box of a zirconium-base alloy by a beta-quench treatment that heats the fuel channel box by a heating coil. The distance between the...
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