Handling Of Fission Reactor Component Structure Within Reactor System Patents (Class 376/260)
  • Patent number: 10290382
    Abstract: A method for preparing to reload a fast nuclear reactor with heavy liquid metal coolant includes extracting a reactor plug and extracting a removable reactor block. The method includes installing handling equipment to form an unloading path under radiation safety conditions. The reactor plug is extracted from the reactor monoblock housing and transported to a plug shaft. The removable reactor block is extracted from the reactor monoblock housing and transported to a block shaft for later disassembly.
    Type: Grant
    Filed: April 17, 2015
    Date of Patent: May 14, 2019
    Assignee: Joint Stock Company “AKME-ENGINEERING”
    Inventors: Nikolay Dmitrievich Vasil'yev, Vladimir Evgen'yevich Ogurtsov, Alexandr Ivanovich Kuznetsov
  • Patent number: 10204710
    Abstract: A control rod drive replacement device includes a channel for mounting on a support under a nuclear reactor pressure vessel and a control rod drive extractor removably received in the channel. The control rod drive extractor includes a base and a housing pivotably connected to the base. The housing is configured for receiving a control rod drive. The base includes a base axis. The housing is pivotably attached to the base at the base axis for pivoting between a horizontal orientation in which the housing is aligned within the channel and a vertical orientation in which the housing is aligned for receiving the control rod drive from the nuclear reactor pressure vessel. The housing is vertically movable with respect to the base in the vertical orientation.
    Type: Grant
    Filed: September 1, 2015
    Date of Patent: February 12, 2019
    Assignee: Framatome Inc.
    Inventors: Kurt David Klahn, Patrick Gruenewald, Dorian Tim Lambert
  • Patent number: 10186335
    Abstract: An automated high speed under vessel work platform with three automated axes comprising a 360° rotational horizontal axis, a linear horizontal axis via a traversing trolley, and a linear vertical axis via swappable task robots, which can also add fourth and fifth axes capabilities. The automated high speed under vessel work platform has the ability to drive to a specific location by typing the core location into the control software. The work platform can be operated manually via a hand wheel, or locally via a handheld pendant or from the control room. The work platform also has a camera for inspections and verification of the work.
    Type: Grant
    Filed: July 14, 2015
    Date of Patent: January 22, 2019
    Assignee: Westinghouse Electric Company LLC
    Inventor: David Platt Ketcham
  • Patent number: 10102935
    Abstract: A lifting fixture for removing the upper internals from a nuclear reactor to provide access to the core during a refueling that does not require flooding of a refueling canal. A shield plate is integral to a lifting rig used to remove the upper internals. The shield plate is sized to be supported on the reactor vessel upper flange and to cover the reactor vessel opening with the closure head removed. The shield plate has openings that are in-line with the control rod assembly drive rod travel housings. Control rod assembly drive rods can be accessed through the openings. The lifting rig allows personnel to decouple the drive rods from the rod cluster control assemblies. The lifting fixture enables the decoupled drive rods to be lifted from the core with the upper internals, while shielding maintenance personnel without flooding the area above the reactor.
    Type: Grant
    Filed: March 10, 2016
    Date of Patent: October 16, 2018
    Assignee: Westinghouse Electric Company LLC
    Inventor: Alexander W. Harkness
  • Patent number: 10096388
    Abstract: A control rod guide frame has a central passage of constant cross-section as a function of position along a central axis that passes through the central passage. The central passage is sized and shaped to guide a traveling assembly including at least one control rod as it moves along the central axis. The control rod guide frame comprises at least two radial guide frame sections secured around and defining the central passage. Each radial guide frame section may comprise an extruded radial guide frame section, which may be made of extruded steel. The central passage may include control rod guidance channels parallel the central axis and machined into the extruded radial guide frame sections. The at least two radial guide frame sections may be interchangeable. In some embodiments the at least two radial guide frame sections consist of between four and eight radial guide frame sections.
    Type: Grant
    Filed: March 17, 2014
    Date of Patent: October 9, 2018
    Assignee: BWXT mPower, Inc.
    Inventor: Scott J Shargots
  • Patent number: 10090071
    Abstract: A system for disposing of one or more radioactive components from a nuclear reactor may include a first receptacle configured to receive the one or more radioactive components, a frame configured to support the first receptacle in the nuclear reactor, and a device configured to separate the one or more radioactive components into two or more portions during lowering of the one or more radioactive components into the first receptacle. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components, and moving the assembled system to an area of a reactor core. A method for disposing of one or more radioactive components from a nuclear reactor may include assembling a system for disposing of the one or more radioactive components in an area of a reactor core.
    Type: Grant
    Filed: December 28, 2012
    Date of Patent: October 2, 2018
    Assignee: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC
    Inventors: Michael Joseph Gundrum, Chris Swick, Joseph Capobianco
  • Patent number: 10037824
    Abstract: A pressurized water nuclear reactor (PWNR) includes a core having a containment shield surrounding a reactor vessel having fuel assemblies that contain fuel rods filled with fuel pellets, and control rods, and a steam generator thermally coupled to the reactor vessel. A flow loop includes the steam generator, a turbine, and a condenser, and a pump for circulating a water-based heat transfer fluid in the loop. The heat transfer fluid includes a plurality of nanoparticles having at least one carbon allotrope or related carbon material dispersed therein, such as diamond nanoparticles.
    Type: Grant
    Filed: March 26, 2014
    Date of Patent: July 31, 2018
    Assignee: UNIVERSITY OF FLORIDA RESEARCH FOUNDATION, INC.
    Inventors: Ronald H. Baney, James S. Tulenko, Kevin W. Powers
  • Patent number: 10014083
    Abstract: A method of refueling a nuclear reactor that includes the steps of removing the reactor vessel head and upper internals to a storage location and installing a cylindrical tank having open upper and lower ends, on the reactor vessel flange. The cylindrical tank is sealed to the reactor vessel and a penetration on the side of the cylindrical tank is sealed to a refueling canal that is connected to a spent fuel pool. The level of reactor coolant within the reactor vessel is then raised to at least partially fill the cylindrical tank to a level equal to that of the spent fuel pool. The refueling canal is then opened and a refueling machine supported on the reactor vessel is employed to transfer fuel assemblies between the core and the spent fuel pool.
    Type: Grant
    Filed: May 2, 2012
    Date of Patent: July 3, 2018
    Assignee: Westinghouse Electric Company LLC
    Inventors: Alexander W. Harkness, William Edward Cummins
  • Patent number: 9997040
    Abstract: Disclosed is a disaster warning device with a guided surface wave receive structure, an impedance matching network, a power circuit, a data processing circuit, and a warning output. The power circuit and the data processing circuit may be coupled to the guided surface wave receive structure. The power circuit may supply electrical energy to power to the data processing circuit and warning output. The power circuit may receive power from a guided surface wave. The data processing circuitry may receive data communications from a guided surface wave.
    Type: Grant
    Filed: September 8, 2015
    Date of Patent: June 12, 2018
    Assignee: CPG Technologies, LLC
    Inventors: James F. Corum, Kenneth L. Corum, Basil F. Pinzone, Jr., Joseph F. Pinzone, Michael J. D'Aurelio
  • Patent number: 9966155
    Abstract: An apparatus for reinforcing a jet pump riser includes: an elbow upper clamp for covering a riser elbow coupled to a thermal sleeve from an upper side thereof; an elbow lower clamping member for clamping the riser elbow from a lower side thereof; an elbow vertical portion clamping member for covering a vertical portion of the riser elbow; and an elbow horizontal portion clamping member for covering a horizontal portion of the riser elbow. These members are disposed in different orientations with respect to the elbow upper clamp so as to fix the thermal sleeve, the riser elbow and the riser pipe.
    Type: Grant
    Filed: March 11, 2014
    Date of Patent: May 8, 2018
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Masakazu Abura, Toshihiro Yasuda, Kazuo Sudo, Haruhiko Hata, Yasushi Kanazawa, Kunihiko Kinugasa, Hajime Mori
  • Patent number: 9922739
    Abstract: A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement.
    Type: Grant
    Filed: November 10, 2015
    Date of Patent: March 20, 2018
    Assignee: Westinghouse Electric Company LLC
    Inventor: Alexander W. Harkness
  • Patent number: 9887017
    Abstract: A nuclear facility comprising an anchor device is provided. This anchor device comprises a female part and a male part. The female part includes a groove extending along a longitudinal axis. The groove has a width which decreases longitudinally and a transverse section. The male part includes a slider with a shape mating that of the groove and is able to be longitudinally inserted into the groove. The transverse section of the groove is configured so as to prevent the extraction of the slider out of the groove transversely to the longitudinal axis. The anchor device includes a locking device able to prevent the slider from longitudinally sliding out of the groove.
    Type: Grant
    Filed: December 23, 2013
    Date of Patent: February 6, 2018
    Assignee: AREVA NP
    Inventors: Luc Bresous, Serge Roillet
  • Patent number: 9773572
    Abstract: A nuclear reactor can include a pressure vessel for containing a pressurized moderator at a first pressure. The nuclear reactor can also include a plurality of fuel channels for a coolant fluid at a second pressure. The plurality of fuel channels are fluidly connected at inlet ends thereof to a coolant supply conduit and are adapted to receive nuclear fuel bundles and to be mounted within the pressure vessel and surrounded by the moderator. The outlet ends of the fuel channels are fluidly connected to a coolant outlet conduit to enable the coolant fluid to circulate from the coolant supply conduit through the fuel channels to the coolant outlet conduit. The plurality of fuel channels maintain separation between the coolant fluid circulating within the fuel channels and the moderator.
    Type: Grant
    Filed: April 21, 2011
    Date of Patent: September 26, 2017
    Assignee: Atomic Energy of Canada Limited
    Inventors: Robert Bodner, Jonathan Tyo, Dan Popov, Sermet Kuran
  • Patent number: 9524804
    Abstract: A control room for a nuclear power plant including two or more nuclear reactor units includes a central workstation providing monitoring capability for both nuclear reactor units, a first operator at the controls (OATC) workstation in front of and to one side of the central workstation providing monitoring and control capabilities for the first nuclear reactor unit, a second OATC workstation in front of and to the other side of the central workstation providing monitoring and control capabilities for the second nuclear reactor unit, and a common control workstation directly in front of the central workstation providing monitoring and control capabilities for systems serving both the first nuclear reactor unit and the second nuclear reactor unit. The central and common control workstations do not provide control capabilities for either nuclear reactor unit. The common control workstation does not include any control capabilities that must be performed by a licensed operator.
    Type: Grant
    Filed: April 11, 2013
    Date of Patent: December 20, 2016
    Assignee: BWXT mPower, Inc.
    Inventor: Thomas G Graham
  • Patent number: 9520477
    Abstract: A semiconductor device includes a substrate, a first and second source/drain regions, and a gate stack. The first and second source/drain regions are disposed on the substrate. The gate stack is disposed over the substrate to overlay a channel region between the first and second S/D regions. The gate stack includes a gate dielectric layer disposed over the substrate; and a metal alloy disposed on the gate dielectric layer and configured as a filling layer in the gate stack; wherein the metal alloy has a first corrosion resistance corresponding to an etchant designed for removing a carbon-containing polymer.
    Type: Grant
    Filed: March 16, 2015
    Date of Patent: December 13, 2016
    Assignee: Taiwan Semiconductor Manufacturing Company
    Inventors: Chi-Cheng Hung, Yu-Sheng Wang, Kei-Wei Chen, Ying-Lang Wang
  • Patent number: 9490036
    Abstract: A control rod for a nuclear boiling water reactor is described. The control rod has a longitudinal centre axis and control rod blades, each control rod blade having a first and a second side and being substantially parallel to the longitudinal center axis. Each control rod blade comprises an absorber material which extends from a first absorber end to a second absorber end, the distance between the first absorber end and the second absorber end defining an active length. The control rod blades are provided with distance means on the first and second sides of the control rod blades, the distance means extending a distance of at least a third of the active length of the control rod blade.
    Type: Grant
    Filed: April 5, 2011
    Date of Patent: November 8, 2016
    Assignee: Westinghouse Electric Sweden AB
    Inventors: Sture Helmersson, Lars Hallstadius
  • Patent number: 9460817
    Abstract: Apparatus for replacing a support pin for a control rod cluster guide tube. The support pin can fix the guide tube to a core plate. The apparatus can be used submerged in water. A movement device can hold and move the guide tube along a frame. A retrieval manipulator can remove an old support pin from the guide tube. A supply manipulator can provide a new support pin to the guide tube. A rotating means imparts rotation for loosening a nut from an old support pin, and for tightening a nut to a new support pin. A control device calculates variation in distance between the nut and the support pin on the basis of the rotation. The control device controls movement of the guide tube along the frame.
    Type: Grant
    Filed: August 2, 2012
    Date of Patent: October 4, 2016
    Assignee: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Tomochika Hamamoto, Norimasa Mori, Yoshiyuki Miyoshi
  • Patent number: 9437333
    Abstract: This invention concerns robotic systems and is specifically concerned with an improved apparatus and method for remotely positioning a sensor, such as an ultrasonic probe, in limited access areas within a nuclear reactor. The apparatus includes a bottom frame and a top cover which is substantially aligned with and positioned above the bottom frame. A sensor is connected to the top cover and linear rails are connected to the bottom frame in a parallel relationship. There is a mechanism movably connected to the first and second linear rails in order to allow horizontal travel of the top cover. Further, there is at least one cable connected to the sensor and a power source, signal source or receiver.
    Type: Grant
    Filed: March 14, 2013
    Date of Patent: September 6, 2016
    Assignee: Westinghouse Electric Company LLC
    Inventor: Kevin J. Foley
  • Patent number: 9404773
    Abstract: Apparatus and method for inspecting pipeline are provided. The pipeline inspecting apparatus moving along an external circumferential surface of a pipeline to inspect the pipeline, includes: a main frame having an arc shape having an opened portion to surround the pipeline; a main movement unit that is movably installed on the main frame, wherein the main movement unit is movably installed along a length direction of the pipeline while being in contact with the external circumferential surface of the pipeline; an auxiliary frame that has an arc shape having an opened portion to surround the pipeline and is separated from the main frame to face the main frame; an auxiliary frame adjusting unit that movably connects the auxiliary frame to the main movement unit in a circumferential direction of the pipeline; and a sensor adjusting unit that is fixed to the auxiliary frame, wherein a sensor for inspecting a state of the pipeline is installed.
    Type: Grant
    Filed: July 13, 2012
    Date of Patent: August 2, 2016
    Assignee: KEPCO ENGINEERING & CONSTRUTION COMPANY, INC.
    Inventors: Hyun Young Chang, Dong Wook Kim, Heung Bae Park, Sang Heon Lee
  • Patent number: 9355749
    Abstract: A device for the dry handling of nuclear fuel assemblies is provided. The device includes a transfer basket which can be connected to a lifter and which includes a gripper for gripping the fuel assembly to be transferred, the gripper being supported by a lift built into the basket; and an indexing table which can be placed on a cask and which comprises a positioner for positioning the basket over a slot in the cask.
    Type: Grant
    Filed: September 14, 2011
    Date of Patent: May 31, 2016
    Assignee: AREVA NP
    Inventors: Mathieu Jean Maurice Chassignet, Frederic Jean-Marie Schermesser
  • Patent number: 9293229
    Abstract: A system for storing high level radioactive waste. In one embodiment, the invention can be a system comprising an overpack body extending along a vertical axis and having a cavity for storing high level radioactive waste, the cavity having an open top end and a floor; an overpack lid positioned atop the overpack body to enclose the open top end of the cavity; an air inlet vent for introducing cool air into the cavity, the air inlet vent extending from an opening in an outer surface of the overpack body to an opening in the floor; and an air outlet vent in the overpack lid for removing warmed air from the cavity.
    Type: Grant
    Filed: November 6, 2014
    Date of Patent: March 22, 2016
    Inventors: Krishna P. Singh, John D. Griffiths
  • Patent number: 9284163
    Abstract: In a movement control apparatus manipulation can be carried out while watching the movement of the moving body, without needing to watch one's hands, so even a novice operator can perform the manipulation easily, safely, reliably, and quickly. The apparatus can include a signal transmission cable, a casing of a manipulation remote controller disposed at one end of the cable, a rotary encoder that produces a signal corresponding to the direction of the casing, and a motor drive control circuit that is disposed on the other side of the cable and controls the movement of a moving body on the basis of a signal corresponding to the direction of the casing. The signal corresponding to the direction of the casing can be supplied from the rotary encoder, through the cable, to the motor drive control circuit.
    Type: Grant
    Filed: January 13, 2014
    Date of Patent: March 15, 2016
    Assignee: GOGOU CO., LTD.
    Inventors: Fujioki Yamaguchi, Kouji Ogawa
  • Patent number: 9208908
    Abstract: A shroud support of a BWR includes a shroud support cylinder, shroud support legs welded to a bottom of a reactor pressure vessel (RPV) and a shroud support cylinder, and an annular shroud support plate disposed between the RPV and the shroud support cylinder and welded to the RPV and the shroud support cylinder. A support apparatus is set a CRD housings installed to the bottom of the RPV. A rail guide member horizontally set to the support apparatus reaches directly below the shroud support plate through an opening between the shroud support legs. A bent rail is set on the rail guide member. The bent rail setting a repair device is pushed out along the rail guide member toward the RPV through the opening portion by the rail push-out apparatus set on the support apparatus. The bent rail is spread at directly below the shroud support plate.
    Type: Grant
    Filed: January 30, 2013
    Date of Patent: December 8, 2015
    Assignee: Hitachi-GE Nuclear Energy, Ltd.
    Inventors: Shinya Ohmori, Koichi Kurosawa, Masaaki Tanaka, Takanori Satoh
  • Patent number: 9109722
    Abstract: The present invention provides an apparatus for detecting and/or repositioning annulus spacers used to maintain the position of a pressure tube withm a calandria tube of a nuclear reactor. The method comprises the steps of: vibrationally isolating a section of the pressure tube; vibrating the wall of said pressure tube within said isolated section; detecting vibration of the wall at a minimum of two axial positions within said isolated sections; and detecting the reduction in vibration level of the wall at one or more of said axial positions in comparison to the remaining axial positions. The apparatus comprises a tool head to be inserted into the pressure tube, the tool head comprising a first end and a second and a clamping block m each of said ends. The clamping blocks are used to vibrationally isolate a section of the pressure tube located between said ends.
    Type: Grant
    Filed: September 10, 2008
    Date of Patent: August 18, 2015
    Assignee: ATOMIC ENERGY OF CANADA LIMITED
    Inventors: James M. King, Bruce A. W. Smith, Paul Feenstra
  • Patent number: 9053828
    Abstract: A method for removing and replacing a bottom-mounted instrumentation nozzle on a nuclear reactor pressure vessel. The method (i) caps or plugs the existing bottom-mounted instrumentation nozzle; (ii) cuts the nozzle at or near the nozzle to in-core instrument tube weld; (iii) installs a water-tight sealing enclosure outside the vessel over the bottom of the bottom-mounted instrumentation nozzle creating a water-tight seal with the underside of the reactor vessel; (iv) cuts to sever the existing bottom nozzle from the reactor vessel; (v) extracts the existing nozzle; (vi) installs a replacement alloy 690 nozzle or plug from inside the vessel; and (vii) welds the replacement nozzle or plug in place. The replacement bottom-mounted instrumentation nozzle incorporates an integral shoulder that prevents ejection during operation and facilitates installation, and the entire method is performed while the reactor pressure vessel is filled with water.
    Type: Grant
    Filed: March 11, 2013
    Date of Patent: June 9, 2015
    Assignee: Westinghouse Electric Company LLC
    Inventors: Bruce R. Newton, Mihai A. Pelle
  • Patent number: 9025720
    Abstract: A CRDS unlatching tool includes a support assembly and a latching assembly, wherein the support assembly is received within the latching assembly in a manner wherein the latching assembly is moveable relative to the support assembly. The support assembly has a plurality of latch fingers and at least one pin, each of the latch fingers being movable between a latched position wherein the latch finger is structured to engage and hold the CRDS an unlatched position wherein the latch finger is structured to not engage the CRDS. The latching assembly includes a first sleeve member and a second sleeve member, the second sleeve member having at least one slot, wherein the at least one pin is moveably received within the at least one slot. The latching assembly is movable from a latched state to an unlatched state wherein the latch fingers are actuated by the first sleeve member.
    Type: Grant
    Filed: June 2, 2011
    Date of Patent: May 5, 2015
    Assignee: Westinghouse Electric Company LLC
    Inventor: Louis J. Tylman
  • Patent number: 9011613
    Abstract: Illustrative embodiments provide systems, methods, apparatuses, and applications related to annealing nuclear fission reactor materials.
    Type: Grant
    Filed: April 16, 2013
    Date of Patent: April 21, 2015
    Assignee: TerraPower, LLC
    Inventors: Charles E. Ahlfeld, John Rogers Gilleland, Roderick A. Hyde, David G. McAlees, Jon David McWhirter, Ashok Odedra, Clarence T. Tegreene, Joshua C. Walter, Kevan D. Weaver, Charles Whitmer, Lowell L. Wood, Jr., George B. Zimmerman
  • Patent number: 9001958
    Abstract: The present invention provides a system and method for reclaiming energy from the heat emanating from spent nuclear fuel contained within a canister-based dry storage system. The inventive system and method provides continuous passive cooling of the loaded canisters by utilizing the chimney-effect and reclaims the energy from the air that is heated by the canisters. The inventive system and method, in one embodiment, is particularly suited to store the canisters below-grade, thereby utilizing the natural radiation shielding properties of the sub-grade while still facilitating passive air cooling of the canisters. In another embodiment, the invention focuses on a special arrangement of the spent nuclear fuel within the canisters so that spent nuclear fuel that is hotter than that which is typically allowed to be withdrawn from the spent fuel pools can be used in a dry-storage environment, thereby increasing the amount energy that can be reclaimed.
    Type: Grant
    Filed: April 21, 2011
    Date of Patent: April 7, 2015
    Inventors: Krishna P. Singh, John D. Griffiths, Debabrata Mitra-Majumdar
  • Patent number: 8995603
    Abstract: A control rod/fuel support handling apparatus that is used in the case where a control rod and a fuel support are held, removed and lifted in a reactor and then are transported into the reactor in a periodical inspection of a BWR and in the case where the control rod and the fuel support are attached and mounted again into the reactor, the control rod/fuel support handling apparatus including: a fuel support gripper that holds the fuel support with a support gripping member; a control rod gripper that includes a vertically movable and rotatable elevating/rotating unit, holds the control rod with a control rod gripping member, disconnects and connects the control rod and a control rod drive mechanism, and allows removal and attachment of the control rod; and a control panel that controls automatically controls the control rod gripper in response to the instructions from an operation pendant.
    Type: Grant
    Filed: December 18, 2009
    Date of Patent: March 31, 2015
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Tsutomu Tomatsu, Koichi Soma, Kaoru Takagi
  • Patent number: 8995605
    Abstract: A lid frame for a nuclear fuel assembly shipping container and a shipping container for nuclear fuel assemblies are provided. The shipping container can include a lower container in which a cradle is installed, an upper container detachably coupled to the lower container, and a base frame coupled to the cradle with at least one nuclear fuel assembly placed thereon. The lid frame can include a plurality of supports installed apart from each other so as to surround the nuclear fuel assembly placed on the base frame, and a plurality of clamps separated from each other, coupled to the plurality of supports perpendicular to the plurality of supports, rotatably hinged to the base frame, and configured to clamp the nuclear fuel assembly. The lid frame safely protects the nuclear fuel assembly that is being transported.
    Type: Grant
    Filed: December 27, 2010
    Date of Patent: March 31, 2015
    Assignee: Kepco Nuclear Fuel Co., Ltd.
    Inventors: Hung Soon Chang, Chang Hwan Hwang, Deuk Yeon Kim, Jae Soon Choi, Weon Chan Hwang, Se Yong Shin, Young Hoon Kim, Jong Sung Hong
  • Patent number: 8989338
    Abstract: A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central ser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum, A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.
    Type: Grant
    Filed: May 17, 2011
    Date of Patent: March 24, 2015
    Assignee: Babcock & Wilcox mPower, Inc.
    Inventor: Scott J. Shargots
  • Publication number: 20150071397
    Abstract: A system, method and apparatus for remotely installing a flange cover assembly on a fuel transfer tube fixed flange in a containment pit in a nuclear power plant is presented. In one example, the flange cover assembly includes J-bolt spring assemblies in which the feet of the J-bolt are rotated between a clamping and non-clamping orientation to engage with the rear face of the fixed flange. A tool frame is lowered into the containment pit to engage with the flange cover assembly to compress the J-bolt springs and extend the J-bolt foot toward and away from the flange cover. Dual acting cylinders move a spring compression frame on the frame tool to compress and relax the J-bolt spring assemblies.
    Type: Application
    Filed: June 17, 2014
    Publication date: March 12, 2015
    Inventor: Bernard DeFazio, JR.
  • Patent number: 8973265
    Abstract: According to an installation method of a water-chamber working apparatus of the present invention, the water-chamber working apparatus includes a base that holds heat transfer tubes on a tube plate surface and is fixed to the tube plate surface, and a manipulator that is coupled with the base, suspended in a water chamber and arranged therein, and has a separable configuration. In this case, a base installing step of installing the base on the tube plate surface and a manipulator coupling step of carrying the separated manipulator (a front stage and a rear stage) into the water chamber sequentially and individually and coupling the manipulator with the base (a coupling link) are performed.
    Type: Grant
    Filed: December 20, 2010
    Date of Patent: March 10, 2015
    Assignee: Mitsubishi Heavy Industries, Ltd.
    Inventors: Jun Fujita, Yoshifumi Isozaki, Atsushi Kamiyoshi
  • Patent number: 8971474
    Abstract: Exemplary embodiments provide automated nuclear fission reactors and methods for their operation. Exemplary embodiments and aspects include, without limitation, re-use of nuclear fission fuel, alternate fuels and fuel geometries, modular fuel cores, fast fluid cooling, variable burn-up, programmable nuclear thermostats, fast flux irradiation, temperature-driven surface area/volume ratio neutron absorption, low coolant temperature cores, refueling, and the like.
    Type: Grant
    Filed: March 16, 2009
    Date of Patent: March 3, 2015
    Assignee: TerraPower, LLC
    Inventors: John Rogers Gilleland, Roderick A. Hyde, Muriel Y. Ishikawa, Nathan P. Myhrvold, Lowell L. Wood, Jr.
  • Patent number: 8964927
    Abstract: Embodiments of the present invention provide a method, a device and a system for communication between double central processing units, which relates to the field of mobile communications technologies. An embodiment of the present invention provides a method for communication between double central processing units, where the method includes: receiving, by a baseband function module, a baseband function invocation request message sent by an application function module through a service channel and a virtual channel, where the baseband function invocation request message carries a virtual channel identifier, and the virtual channel identifier corresponds to the virtual channel; and in response to the baseband function invocation request message, returning, by the baseband function module, a baseband function invocation response message to the application function module, where the baseband function invocation response message carries the virtual channel identifier.
    Type: Grant
    Filed: October 19, 2012
    Date of Patent: February 24, 2015
    Assignee: Huawei Device Co., Ltd.
    Inventor: Jianbing Zheng
  • Patent number: 8958519
    Abstract: A nuclear reactor comprises a pressure vessel, a nuclear reactor core comprising fissile material disposed in the pressure vessel, and a core basket disposed in the pressure vessel and containing the nuclear reactor core. An incore instrument is disposed in a guide tube of the nuclear reactor core. The incore instrument has a cable extending out of the bottom of the nuclear reactor core and making a 180° turn. A bottom support element is attached to the bottom of the core basket and defines or includes a routing tube that routes the cable of the incore instrument through the 180° turn. In some embodiments, the pressure vessel includes upper and lower vessel portions, the nuclear reactor core and core basket are disposed in the lower vessel portion, and the vessel penetration is through the lower vessel portion or through a mid-flange connecting the upper and lower vessel portions.
    Type: Grant
    Filed: November 5, 2012
    Date of Patent: February 17, 2015
    Assignee: Babcock & Wilcox mPower, Inc.
    Inventors: Andrew C. Whitten, Michael J. Edwards
  • Patent number: 8953733
    Abstract: A method for joint configuration of nuclear power plant fuel includes the following steps: (S1) for at least one operating unit, based on an equilibrium cycle or transition cycle reactor core design, at least one new fuel element is added to at least one operating unit; (S2) after running a combustion cycle, and on basis of the new fuel elements in step (S1), more first spent fuel elements are obtained from the at least one operating unit than are obtained from the equilibrium cycle or transition cycle reactor core design, and said first spent fuel elements are kept in reserve; (S3) for at least one new starting unit, a scheduled number of new fuel elements, as well as the first spent fuel elements obtained for reserve in step (S2), are set in the first reactor cores of at least one new starting unit.
    Type: Grant
    Filed: May 21, 2010
    Date of Patent: February 10, 2015
    Assignees: China Nuclear Power Engineering Compay Ltd., China Nuclear Power Technology Research Institute, China Guangdong Nuclear Power Holding Corporation
    Inventor: Zirong Ma
  • Patent number: 8938044
    Abstract: A robotic tubesheet walker having two rails connected by a central hinge, wherein the central hinge can be opened or closed by an actuation device. Upon each rail is mounted a carriage, wherein each carriage can move along its respective rail toward or away from the central hinge by means of a drive mechanism. Each carriage further contains at least two “gripper” attachment mechanisms, such as camlocks, to grip the tubesheet. The grippers either insert into tube holes within the tubesheet to fasten the respective carriage to the tubesheet, or retract to disengage. Further attached to the central hinge is a tool support fixture, and attached to the tool support fixture is a coupler that holds maintenance or inspection tools.
    Type: Grant
    Filed: February 25, 2013
    Date of Patent: January 20, 2015
    Assignee: Westinghouse Electric Company LLC
    Inventors: Lyman J. Petrosky, Phillip J. Hawkins
  • Publication number: 20150016582
    Abstract: The cooling duct assembly for a control element drive mechanism (CEDM) includes a skirt that is combined on a circumference of a reactor head and has first air channels in an inner side thereof; a lower duct that is combined with an upper side of the skirt, has second air channels that are connected to the first air channels, and is disposed to surround a circumference of the CEDM; and an upper duct, an edge of which is combined with the cooling air handling device, and other edge of which is detachably combined with the lower duct, wherein air that cools the CEDM is discharged to the outside after sequentially passing the first air channels, the second air channels, the upper duct, and the cooling air handling device, and the upper duct separated from the lower duct is lifted together with the cooling air handling device.
    Type: Application
    Filed: July 2, 2014
    Publication date: January 15, 2015
    Inventors: Myoung Goo LEE, Woo Cheol CHOI, Yeon Ho CHO
  • Patent number: 8934600
    Abstract: A pressurizer is for a pressurized water nuclear power plant and it includes an upper cap provided with a tube; an end piece connected to the tube using a weld; and a sleeve protecting the weld, disposed inside the tube. The protective sleeve is mounted in a removable manner, such that the thermal sleeve is removed.
    Type: Grant
    Filed: March 14, 2008
    Date of Patent: January 13, 2015
    Assignee: Areva NP
    Inventor: Sébastien Michel Marie Petit-Jean
  • Patent number: 8934601
    Abstract: A method and apparatus for grasping and lifting a boiling water reactor (BWR) control rod using a grapple. The grapple may grasp the control rod blade, the fuel support casting and the control rod guide tube of the control rod, to lift and move all three of these components in unison. The grapple includes a frame, a control rod blade hook, a fuel support casting hook(s) and a control rod guide tube hook(s). The control rod guide tube hook(s) may have a distal end that extends through a side flow orifice of a fuel support casting and beyond the confines of a control rod guide tube flow orifice to grasp the control rod guide tube. The distal end of the control rod guide tube hook(s) may include inner and outer landing surfaces, providing respective support for the fuel support casting and control rod guide tube.
    Type: Grant
    Filed: September 30, 2011
    Date of Patent: January 13, 2015
    Assignee: GE-Hitachi Nuclear Energy Americas LLC
    Inventors: Robert W. Whitling, Michael Joseph Gundrum, Mark D. Bardeen, Gregory A. Francisco
  • Patent number: 8917808
    Abstract: The invention refers to a device and a method for handling a fuel assembly (3), which comprises a number of fuel rods extending between a lower part and an upper part of the fuel assembly, a debris filter located in the lower part of the fuel assembly and a casing surrounding the fuel rods. The device comprises a lifting device (15) for engaging, during a lifting operation, a fuel assembly located in a reactor vessel (1) and lifting the fuel assembly upwards and out from the reactor vessel. A conduit member is connected to the upper part of the fuel assembly. A pump (32) creates a flow of water through the conduit member and the fuel assembly during the lifting operation. The flow has such a size that possible debris particles contained in and/or immediately beneath the debris filter at least are retained in and/or immediately beneath the debris filter during the lifting operation.
    Type: Grant
    Filed: August 21, 2007
    Date of Patent: December 23, 2014
    Assignee: Westinghouse Electric Sweden AB
    Inventor: Sture Helmersson
  • Patent number: 8913708
    Abstract: A maintenance/repair device for reactor internal structure 6 of the present invention includes a device body 6a configured to be fixed on a reactor internal structure 49. Connected to the device body 6a is a welding-part repair mechanism 6b configured to repair a welding part 49a of the reactor internal structure 49. Thus, a welding part 2a of the reactor internal structure 49 can be repaired by the welding-part repair mechanism 6b, while the device body 6a is fixed on the reactor internal structure 49.
    Type: Grant
    Filed: November 16, 2012
    Date of Patent: December 16, 2014
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Yoshiaki Ono, Hidekazu Sasaki, Takuya Uehara, Hiromi Kato, Toshihiro Yasuda
  • Publication number: 20140362967
    Abstract: A reactor measurement-pipe maintenance clamp apparatus includes a first clamp mechanism and a second clamp mechanism. The first clamp mechanism includes clamps to fix the measurement pipe between the clamps, first clamp operation bolts that are allowed to be turned by remote control from above a reactor core, and wedge mechanisms to convert the turning of the clamp operation bolts to displacement of the clamps in a radial direction of the diffuser to generate clamping forces for securing the measurement pipe. The second clamp mechanism includes a support clamp to hold the support, a second clamp operation bolt that is allowed to be turned by remote control from above the reactor core, and a wedge mechanism to convert the turning of the second clamp operation bolt to displacement of the support clamp in a tangential direction of the diffuser to generate clamping force for fixing the support.
    Type: Application
    Filed: July 23, 2014
    Publication date: December 11, 2014
    Inventors: Yusuke OZAWA, Kunihiko Kinugasa, Hajime Mori, Yuki Minato, Masanobu Watanabe, Hiroyuki Adachi, Tadahiro Mitsuhashi
  • Publication number: 20140328444
    Abstract: Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system.
    Type: Application
    Filed: May 22, 2014
    Publication date: November 6, 2014
    Inventors: Charles E. Ahlfeld, Pavel Hejzlar, Roderick A. Hyde, Muriel Y. Ishikawa, David G. McAlees, Jon D. McWhirter, Nathan P. Myhrvold, Ashok Odedra, Clarence T. Tegreene, Joshua C. Walter, Kevan D. Weaver, Thomas Allan Weaver, Charles Whitmer, Lowell L. Wood, JR., George B. Zimmerman
  • Publication number: 20140314195
    Abstract: A lifting shackle of a head assembly for a nuclear reactor according to one embodiment of the present invention comprises: a first member and a second member which extend in parallel to each other in a predetermined thickness and length and respectively have an upper portion and a lower portion; a first connection member which connects the upper portion of the first member and the upper portion of the second member to each other and is coupled to a hook; coupling sections which are respectively provided at the lower portions of the first member and the second members and has a hollow portion so as to be coupled to the head assembly for a nuclear reactor via pins; and stress reducing sections which are formed at the upper portions of the first member and the second member such that the stress reducing sections extend from the first connection member to the first member and the side end of the second member at a predetermined curvature and protrudes upwards so as to reduce bending stress that is applied to the
    Type: Application
    Filed: December 11, 2012
    Publication date: October 23, 2014
    Applicant: DOOSAN HEAVY INDUSTRIES & CONSTRUCTION CO., LTD.
    Inventors: Jung Dae Son, Sung Hwan Kim, Yong Kyu Kim
  • Patent number: 8857027
    Abstract: A method of reducing the volume of a blade section of a boiling water reactor control rod for transport or storage that cuts the control rod spline into four substantially equal longitudinal sections, with each longitudinal section including one control rod blade. Each longitudinal section is radiologically characterized and the locations of desired lateral segmentation are identified. A band of malleable metal is wrapped around each longitudinal section at each of the locations and the bands are sheared to separate segments of the longitudinal section and the ends of the bands are crimped at the point of shearing to seal the interior of the segments.
    Type: Grant
    Filed: September 13, 2012
    Date of Patent: October 14, 2014
    Assignee: Westinghouse Electric Company LLC
    Inventor: Peter F. Davin
  • Patent number: 8842801
    Abstract: A rod assembly for a fuel bundle of a nuclear reactor may include an upper end piece, lower end piece and a plurality of rod segments attached between the upper and lower end pieces and to each other so as to form an axial length of the rod assembly. The rod assembly may include an adaptor subassembly provided at given connection points for connecting adjacent rod segments or a given rod segment with one of the upper and lower end pieces. The connection points along the axial length of the rod assembly may be located where the rod assembly contacts a spacer in the fuel bundle. One (or more) of the rod segments may include an irradiation target therein for producing a desired isotope when a fuel bundle containing one (or more) rod assemblies is irradiated in a core of the reactor.
    Type: Grant
    Filed: July 30, 2008
    Date of Patent: September 23, 2014
    Assignee: General Electric Company
    Inventors: Russell Morgan Fawcett, Randy Peter Gonzales, Russell Patrick Higgins, Robert Bryant James, Michael Thomas Kiernan, William Earl Russell, II, Steven Bruce Shelton, David Grey Smith, Russell Edward Stachowski, Lukas Trosman
  • Patent number: 8842799
    Abstract: A jet pump which can restrain self-excited vibration in a connection portion between an inlet mixer pipe and a diffuser pipe without inhibiting a structural deformation due to thermal expansion and the like includes a slip joint structure connecting the inlet mixer pipe and the diffuser pipe to each other by inserting the inlet mixer pipe into an upper end opening of the diffuser pipe with a clearance left therebetween; and a self vibration damping structure configured such that when the clearance defined by an outer pipe wall of the inlet mixer pipe and an inner pipe wall of the diffuser pipe is widening or narrowing due to vibration of the inlet mixer pipe or the diffuser pipe, a flow path resistance inside a clearance flow path for pumped coolant water defined by the clearance is not smaller than a fluid inertia force all over the clearance flow path.
    Type: Grant
    Filed: April 2, 2010
    Date of Patent: September 23, 2014
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Masanobu Watanabe, Kunihiko Kinugasa, Tsuyoshi Hagiwara, Masahiko Warashina, Jun Suzuki
  • Patent number: 8824618
    Abstract: Disclosed is an unlatching tool that may be used to unlatch a control rod from a control drive. The unlatching tool may include a baseplate, a first guide member and a second guide member attached to the baseplate, a first frame and a second frame attached to the baseplate, a stepper motor attached to the first frame, a worm drive attached to the first frame, a cable reel shaft attached to the first and second frame, a hose wrapped around the cable reel shaft, and a hook attached to a first end of the hose. The hook may include a cylindrical sleeve having a at least one finger configured to fold and unfold. Disclosed also is a method of unlatching a control rod from a control drive.
    Type: Grant
    Filed: November 10, 2010
    Date of Patent: September 2, 2014
    Assignee: GE-Hitachi Nuclear Energy Americas LLC
    Inventors: Jack Matsumoto, Robert W. Whitling, Christopher M. Welsh, Gregory A. Francisco