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Westinghouse Electric Company LLC Patents
Assignee:
Westinghouse Electric Company LLC
Address:
Monroeville, PA
No. of patents:
122
Patents:


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Patent Number Title Of Patent Date Issued
8571911 Facility life management method October 29, 2013
An improved method of selecting and planning the performance of various maintenance activities on a facility such as a nuclear power plant includes determining the net present value of a number of future net savings that are expected to result from performance of the maintenance acti
8571165 Neutron absorber consisting of refractory metal infused with discrete neutron absorber October 29, 2013
The present invention provides a gray rod control assembly for a nuclear reactor. The gray rod control assembly includes a spider assembly having a plurality of radial extending flukes and a plurality of gray rod assemblies coupled to the flukes of the spider assembly. Each of the gray
8568105 Dynamic port for measuring reactor coolant pump bearing oil level October 29, 2013
A dynamic port that extends from the bottom wall of an oil reservoir that surrounds the lower guide bearing of a reactor coolant pump and is in fluid communication within an oil level gauge. The dynamic port is rotatable into and out of the oil flow path to adjust the dynamic oil lev
8565365 Unirradiated nuclear fuel component transport system October 22, 2013
An unirradiated nuclear fuel assembly and fuel component shipping cask that employs a liner with a universal, removable, reusable axial restraint device that can accommodate various fuel assembly designs. The restraint device has a top shear plate with a groove that encircles its per
8561287 Under vessel local power range monitor exchange tool October 22, 2013
A tool for use in servicing an LPRM assembly of a nuclear reactor vessel includes a structural member having a first bore that is structured to receive an LPRM device associated with the LPRM assembly, a headpiece provided at a first end of the structural member, and a nut engaging a
8293151 Triuranium disilicide nuclear fuel composition for use in light water reactors October 23, 2012
The present invention relates to nuclear fuel compositions including triuranium disilicide. The triuranium disilicide includes a uranium component which includes uranium-235. The uranium-235 is present in an amount such that it constitutes from about 0.7% to about 5% by weight based
8254516 Control rod drive outer filter removal tool August 28, 2012
An outer filter removal tool for a boiling water reactor control rod drive that uses a mechanical advantage obtained through the use of lead screw threads to pull the outer filter off of the control rod drive. Fingers on the tool are closed around the upper flange of the outer filter
8246313 Dynamic port for measuring reactor coolant pump bearing oil level August 21, 2012
A dynamic port that extends from the bottom wall of an oil reservoir that surrounds the lower guide bearing of a reactor coolant pump and is in fluid communication within an oil level gauge. The dynamic port is rotatable into and out of the oil flow path to adjust the dynamic oil lev
8238511 Nuclear fuel assembly protective bottom grid August 7, 2012
A protector bottom grid for a nuclear fuel assembly that includes three laterally staggered and horizontally oriented protrusions that extend into the fuel rod cell of a support grid below a vertically oriented spring. The three staggered protrusions extend into the cell a distance t
8238510 Steam generator dual head sludge lance and process lancing system August 7, 2012
A method of cleaning sludge from the tube sheet (34) of a nuclear steam generator (10) includes introducing a moveable sludge lance (76) said moveable sludge lance having duel lance heads (77) through handholes (62) in the side of the generator and into a central tube lane (60) having a
8233581 Process for adding an organic compound to coolant water in a pressurized water reactor July 31, 2012
The present invention relates generally to a process for a pressurized water reactor. The pressurized water reactor includes a primary circuit and a reactor core. The process includes adding a sufficient amount of an organic compound to coolant water passing through the primary circuit o
8212553 Inspection mode switching circuit July 3, 2012
An eddy current probe testing apparatus structured to operate concurrently in a driver pick-up mode and said impedance mode is provided. The eddy current probe has two coils. The eddy current probe testing apparatus also includes a signal producing device, an output device, and a swi
8156251 Advanced logic system April 10, 2012
The Advanced Logic System (ALS) is a complete control system architecture, based on a hardware platform rather than a software-based microprocessor system. It is significantly different from other PLC-type control system architectures, by implementing a FPGA in the central control un
8149983 Method for analysis of pellet-cladding interaction April 3, 2012
A method is provided for evaluating pellet-cladding interaction (PCI) in a nuclear core having a reactor protection system and a plurality of elongated fuel rods each having fuel surrounded by cladding with a gap therebetween. The method includes: selecting a number of core parameters
8141442 Pipe scanner March 27, 2012
A pipe scanner for non-destructively scanning an extended length of the circumference of a pipe along an axial dimension. The pipe scanner includes a collar sized to fit around the outer circumference of the pipe. Wheels supported on the collar ride on the surface of the pipe while m
8117512 Failure detection and mitigation in logic circuits February 14, 2012
The present invention is directed to methods of monitoring logic circuits for failures. In particular, the methods are directed toward establishing parallel logic cores where failures are detected by comparing the parallel paths for equivalence at key locations by a redundancy checker.
8064564 Neutron shielding panels for reactor pressure vessels November 22, 2011
In a nuclear reactor neutron panels varying in thickness in the circumferential direction are disposed at spaced circumferential locations around the reactor core so that the greatest radial thickness is at the point of highest fluence with lesser thicknesses at adjacent locations wh
8061208 Non-destructive pipe scanner November 22, 2011
A non-destructive examination pipe scanner that employs a main carriage on which a sensor is mounted, a tensioner carriage and an idler carriage. The main carriage and the tensioner carriage are positioned around the pipe at spaced locations and connected on either side by a spring band.
8031826 Neutron absorber consisting of refractory metal infused with discrete neutron absorber October 4, 2011
The present invention provides a gray rod control assembly (GRCA) containing an improved neutron absorber comprised of a porous matrix of refractory metal infused with a neutron absorbing metal or metal alloy for a nuclear reactor. The reactor has a plurality of fuel assemblies, each
8011249 Steam generator nondestructive examination method September 6, 2011
A method of examining a steam generator heat exchange tube from the outside surface employing ultrasonic nondestructive inspection techniques. An ultrasonic transducer contacts the outside surface of the tube and transmits a pseudo helical Lamb wave into the wall of the tube chosen t
7995701 Nuclear core component hold-down assembly August 9, 2011
A plate mounted fuel assembly hold-down system that provides a defined channel for both the insertion and removal of reactor head mounted, fixed in-core detector instrumentation, provides a guided path for the fixed in-core detector during insertion, and shields the instrument shroud
7976693 Hydrogen generation process with dual pressure multi stage electrolysis July 12, 2011
A multi-pressure hybrid sulfur process (2) contains at least one electrolyzer unit (16) which provides liquid H.sub.2SO.sub.4 to a preheater/vaporizer reactor (20) operating at a pressure of from 1 MPa to 9 MPa to form gaseous H.sub.2SO.sub.4 which is passed to a decomposition reacto
7961836 Use of boron or enriched boron 10 in UO.sub.2 June 14, 2011
The present invention provides a nuclear fuel assembly, where a boron-containing compound is used as a burnable poison and is distributed in a majority of the rods in the assembly. The assembly comprises a plurality of fuel rods, each fuel rod containing a plurality of nuclear fuel p
7945011 Enhanced steam dump (bypass) control system May 17, 2011
The present invention relates to a method of controlling a nuclear reactor during a transient period. The method includes actuating the steam dump system in response to a temperature error signal and a power mismatch signal.
7894565 Subcritical reactivity measurement method February 22, 2011
A method of determining the spatially corrected inverse count ratio (SCICR) used to determine reactor criticality, which subtracts a background noise signal from the source range detector output. The method monitors the source range detector signal at two different core temperature l
7889830 Nuclear reactor downcomer flow deflector February 15, 2011
A nuclear reactor having a coolant flow deflector secured to a reactor core barrel in line with a coolant inlet nozzle. The flow deflector redirects incoming coolant down an annulus between the core barrel and the reactor vessel. The deflector has a main body with a front side facing
7889829 Nuclear fuel assembly protective grid February 15, 2011
An integral multilevel debris-catching system for a nuclear reactor fuel assembly having a lower protective grid incorporating laterally offset debris-catching arches at several elevations, extended solid fuel rod bottom end plugs and a bottom debris-filtering nozzle. Dimples and opp
7742555 Enhanced steam dump (bypass) control system June 22, 2010
The present invention relates to a method of controlling a nuclear reactor during a transient period. The method includes actuating the steam dump system in response to a temperature error signal and a power mismatch signal.
7023949 Jet pump assembly repair method April 4, 2006
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 pump against vibrations. The wedge or the bracket is repaired in situ by: providing a spacer l
6931090 Method of establishing a nuclear reactor core fuel assembly loading pattern August 16, 2005
All possible loading patterns for a nuclear reactor core are searched and optimized for compliance with design constraints. The fuel inventory is divided into a few batches according to coarse levels of reactivity. A recursive enumeration process identifies patterns meeting selected core
6909765 Method of uprating an existing nuclear power plant June 21, 2005
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 to handle the increased thermal power. The thermal power of the nuclear island can be i
6888909 Reactor pressure vessel May 3, 2005
A reactor pressure vessel supports the flanges of a core barrel assembly and an upper support plate. These flanges have aligned holes for diverting inlet coolant water to the vessel head for cooling the head. The aligned holes have different cross-sectional areas for controlling unexpect
6886502 Method for controlling steam generators May 3, 2005
A method of controlling the feedwater flow to the secondary side of a steam generator in a pressurized water nuclear reactor monitors various process variables such as the feedwater and the steam flows and pressures around the secondary side of the steam generator and then generates proc
6886407 Nondestructive examination of high pressure turbine cylinders May 3, 2005
A method of inspecting the steam inlet sleeves on high pressure outer cylinders and the nozzle chamber to cylinder welds on the high pressure steam turbines using linear phased array ultrasonic transducers. The transducers are supported on the surface of the component to be monitored.
6842669 Component interface module January 11, 2005
A component interface module (CIM) arbitrates through priority logic component command signals from redundant systems and integrates the selected priority command signal with component feedback signals in component logic to generate a control signal for a component in a complex plant
6823269 Eddy current data union November 23, 2004
A method of synthesizing nondestructive examination data of a component including the steps of generating nondestructive examination data of the component in the field and separately generating nondestructive examination data of a specimen machined to simulate selected flaws in the c
6819733 Fuel assembly and associated grid for nuclear reactor November 16, 2004
An improved grid for use in a fuel assembly of a nuclear reactor includes a plurality of straps that are interconnected with one another in a lattice fashion to define a plurality of cells, with the straps being configured to include a plurality of relatively more compliant springs and a
6801885 Process for synthesizing a database for nuclear power plant containment evaluation October 5, 2004
A method of evaluating a containment building design includes the steps of assembling a first database of test results; selecting models (algorithms) for the design to be evaluated; comparing a first set of test results of the model to test results in the first database of test results;
6801593 Subcritical reactivity measurement method October 5, 2004
A method of monitoring reactivity changes in a nuclear reaction when the nuclear reaction is subcritical. The method controls the parameter of the nuclear reaction that affects reactivity of the reaction to slightly alter the reactivity while monitoring an output of a source range detect
6799124 Method of optimizing risk informed inspections of heat exchangers September 28, 2004
A probabilistic method for optimizing the inspection of a heat exchanger that determines the maximum number of degraded tubes that can be permitted to remain in service for a contemplated interval of time without exceeding an allowable probability of a tube burst, based upon Extreme Valu
6795518 Integral PWR with diverse emergency cooling and method of operating same September 21, 2004
Passive emergency cooling in response to a loss of coolant accident (LOCA) in a PWR, having an integral reactor pressure vessel incorporating the steam generators and housed in a small high pressure containment vessel, is provided by circulating cooling water through the steam generators
6788213 Energize to actuate engineered safety features actuation system and testing method therefor September 7, 2004
A component actuation circuit for an engineered safety features actuation system (ESFAS) includes a plurality of coincidence logic contacts, and a plurality of parallel-connected ESFAS component relays. Each of the coincidence logic contacts closes in response to a command signal. The
6765221 Method and apparatus for shipping substantially pure uranium hexafluoride July 20, 2004
Substantially pure uranium hexafluoride is shipped in a conventional overpack. A cylinder includes a vessel with a cylindrical sidewall A head permanently affixed to the sidewall closes one end of the vessel. A valve controls the flow of matter into and out of the vessel. A sealing surfa
6763570 Method of closing a pressure vessel July 20, 2004
A pressure vessel having a removable closure head in a high radiation environment is closed by placing the closure head having a flange over and spaced from the flange of a pressure vessel body containing fissile material. The closure studs are installed in closure stud holes of the
6748042 Unirradiated nuclear fuel component transport system June 8, 2004
An unirradiated nuclear fuel assembly component transport system that includes a clamshell-type inner liner that opens along its axial dimension to load and unload the fuel component being transported. The exterior dimensions of the liner conform to a generic overpack tubular container.
6738447 High energy absorption top nozzle for a nuclear fuel assembly May 18, 2004
A high energy absorption top nozzle for a nuclear fuel assembly that employs an elongated upper tubular housing and an elongated lower tubular housing slidable within the upper tubular housing. The upper and lower housings are biased away from each other by a plurality of longitudinally
6726140 Take-up reel for flexible elongated members April 27, 2004
Apparatus for delivering energy and material, such as electricity, air and fluid, from a source (22) to a driven device (24). The apparatus (20) comprises at least one flexible elongated member (26) selected from the group of electrical conductors, air hoses, fluid hoses and the like. Th
6721381 Seal arrangement for in-core instrument housing April 13, 2004
A seal arrangement for providing a seal between a nuclear reactor in-core instrument housing and an instrument contained within the housing includes a lower seal assembly surrounding an outer portion of the in-core instrument housing, an upper seal assembly surrounding an outer portion o
6719952 Fluidized bed reaction design April 13, 2004
A fluidized bed reactor (10) for chemically transforming reactants to generate a desired product, having a hollow, elongated, vertically oriented reactor housing (12) for confining the reaction and an unobstructed collection path (18) below the reaction zone for funneling the residue
6683931 Unirradiated nuclear fuel transport system January 27, 2004
An unirradiated nuclear fuel assembly transport canister that includes a clamshell type fuel assembly inner liner that has interior dimensions that closely conform to the outer envelope of the fuel assembly to be transported and exterior dimensions that conform to a generic overpack
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