| Patent Number |
Title Of Patent |
Date Issued |
| 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 |
| 6682358 |
Instrumentation electrical connector protector |
January 27, 2004 |
| Apparatus (20) for installation onto an exposed end (22) of an instrumentation connector (24) in a nuclear reactor, to protect the exposed end of the connector from a surrounding body of liquid. The apparatus includes a shell (32) with a closed first end (34) formed from a liquid res |
| 6674826 |
Method of operating a nuclear power plant at multiple power levels |
January 6, 2004 |
| A method of operating a nuclear power plant includes determining and licensing a maximum power level at which the power plant can be operated subsequent to the beginning of a fuel cycle, and with the power plant being operated at less than its maximum power rating at certain times such |
| 6654436 |
Stud enclosure and method of use |
November 25, 2003 |
| 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 extending hole with a screw extending therein for fastening the stud enclosure to the stud. |
| 6639960 |
Method of retrofitting a reactor pressure vessel head assembly |
October 28, 2003 |
| A head assembly of a reactor pressure vessel in an ice condenser plant is retrofitted to permit the assembly to be removed during a later refueling operation in reduced time and with reduced exposure to radiation by operating personnel. The portions of the ductwork ventilation system tha |
| 6627898 |
Method and system for monitoring radiation and rejecting noise |
September 30, 2003 |
| A method of monitoring a nuclear reactor includes monitoring the nuclear reactor with a plurality of radiation sensors having spaced apart attachments to a radiation hard cable; providing signal processing equipment at each end of the cable for processing signals from the radiation s |
| 6606920 |
Tube non-destructive testing probe drive elevator and contamination containment system |
August 19, 2003 |
| An improved tube inspection probe delivery system that supports a probe pusher that drives a cable connected to the probe through a flexible conduit into a tube for inspection. The probe pusher is mounted on an elevator that advances the probe pusher toward or retracts the probe push |
| 6606369 |
Nuclear reactor with improved grid |
August 12, 2003 |
| An improved grid for use in a fuel assembly of a nuclear reactor includes a plurality of straps connected in a lattice, with a plurality of mixing vanes being disposed on the straps and being arranged such that the hydraulic forces on the mixing vanes generally cancel one another out. Th |
| 6596998 |
Method and system for identifying the source of a signal |
July 22, 2003 |
| A method for determining which of a plurality of detectors transmitted a signal, such as a signal related to neutron or gamma emissions, includes connecting each of the detectors to a single cable, such as an environmentally rugged cable. Signals are transmitted from each of the dete |
| 6578451 |
Remote bolt installation tool |
June 17, 2003 |
| Fastener gripping apparatus (10) can be used in connection with a shaft (14) having a driver portion (80) adapted to engage a bolt (3). The apparatus is used to move the bolt between an uninstalled condition, and an installed condition in a structural member (8). The apparatus can in |
| 6570950 |
Nuclear plant containment with prefabricated component support structure |
May 27, 2003 |
| A nuclear steam supply containment system employing prefabricated component supports that are surrounded by steel concrete forms and anchored to the floor liner of a nuclear containment. The prefabricated component supports extend through the concrete forms and a reinforce concrete slab |
| 6557421 |
Mandrel supported tensile test to evaluate weld bonding |
May 6, 2003 |
| A tensile test apparatus and method for testing a circumferential weld on a tubular member wherein the tube region of the weld is completely supported by a mandrel and the tubular specimen is gripped on both sides of the weld along the specimen's longitudinal length with a very small sep |
| 6532550 |
Process protection system |
March 11, 2003 |
| A protection system for a complex process has four redundant protection sets, each of which produces partial reactor trip and partial safeguard actuation signals in pairs of microprocessor-based controllers. Two independent and redundant voting logic trains are provided for the partial |
| 6526116 |
Nuclear fuel assembly with hydraulically balanced mixing vanes |
February 25, 2003 |
| A support grid for laterally maintaining the relative position of elongated fuel elements within a fuel assembly for use within a core of a nuclear reactor. The grid is formed in the shape of a lattice with the intersecting lattice members defining a plurality of cells, most of which |
| 6522710 |
Fastened spacer for grid of a nuclear reactor with associated method |
February 18, 2003 |
| A spacer for use with a protective grid of a fuel assembly of a nuclear reactor is a generally washer-shaped plate of material having an engagement surface and a retention surface opposite one another. The protective grid is formed of a plurality of straps to define a plurality of fu |
| 6522709 |
Nuclear in-core instrument (ICI) assembly with compressed flexible hose sheath |
February 18, 2003 |
| A protective hose, and a method of making the same, for an in-core instrument assembly used in a nuclear reactor, including a first end that is hermetically sealed to a first member of in-core instrument assembly such as a bullet nose, a second end that is hermetically sealed to a se |
| 6522708 |
Seal arrangement for in-core instrument housing |
February 18, 2003 |
| 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 |
| 6506955 |
Decontamination method |
January 14, 2003 |
| A boiling water reactor is chemically decontaminated by circulating a decontamination solution through reactor recirculation loops and the annulus region of a reactor pressure vessel that surrounds the central core region while bypassing the central core region. The decontamination s |
| 6493412 |
Method of calibrating exit thermocouples in a nuclear reactor |
December 10, 2002 |
| The exit thermocouples of a pressurized water reactor (PWR) are calibrated by recording the thermocouple temperature measurements periodically during power ascension of the reactor together with a predicted power at the corresponding locations at the same time determined by a three-dimen |
| 6492901 |
Alarm management system |
December 10, 2002 |
| An alarm management system and method includes structure and function for receiving one or more process parameter signals representative of one or more process parameters. Each of the received process parameters is then compared with an associated alarm point. An alarm status signal is |
| 6488434 |
Overload indicator |
December 3, 2002 |
| An overload indicator apparatus (10) is provided for use in connection with a force generator (12). The force generator is used to apply a force to a load (14), and the overload indicator will indicate if the applied force is greater than a predetermined amount. The overload indicator in |
| 6484126 |
Digital plant protection system with engineered safety features component control system |
November 19, 2002 |
| A system and method for interfacing with a nuclear power plant's digital plant protection system activates emergency response devices when necessary. Two redundant bistable processors in each of four logic channels determine whether a particular parameter of the plant operation excee |
| 6473479 |
Dual optical communication network for class 1E reactor protection systems |
October 29, 2002 |
| A communication network for nuclear plant protection systems includes monitoring and control channels, including a first pair of channels having first and second channels, the first pair of channels communicating through fiber optic data paths with a second pair of channels having third |
| 6467439 |
Steam generator tube support grid array |
October 22, 2002 |
| An array grid includes a plurality of interlocking elongate strips. The strips are structured and configured to provide sufficient lateral support for steam generator tubing while minimizing the risk of attack by stress corrosion cracking to the steam generator tubes. |
| 6466636 |
Decontamination method |
October 15, 2002 |
| A boiling water reactor having a reactor pressure vessel with two recirculation loops hydraulically connected thereto is decontaminated by installing plugs in the outlets of jet pump ram's head manifolds located within the reactor pressure vessel to isolate the recirculation loops from |
| 6463114 |
Jack screw gap replacement device |
October 8, 2002 |
| A jacking device includes first, second, and third members (51, 52, 53), and a jacking screw (55). The first and second members (51, 52) have sloping side portions (57). The third member (53) has a plurality of sloped side portions (57) and a threaded opening (67) extending from its |
| 6462667 |
Energize to actuate engineered safety features actuation system and testing method therefor |
October 8, 2002 |
| 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 |
| 6459748 |
Floating ultrasonic testing end effector for a robotic arm |
October 1, 2002 |
| An end effector for supporting an ultrasonic testing probe on a robot arm having a robot mounting bracket for use in a nuclear reactor pressure vessel. The end effector has a wrist assembly with a rotatable wrist axle. The wrist assembly is coupled to the robot mounting bracket and a pro |
| 6429649 |
Eddy current testing probe |
August 6, 2002 |
| A replaceable eddy current probe for inspecting small (3/4 inch diameter or smaller) tubes of heat exchangers has a head portion with bobbin coils and a delivery conduit connector portion with a flexible conduit having a first end extending from the head portion and a second end extendin |
