Vessel Support (e.g., Core Vessel Supports) Patents (Class 376/461)
  • Patent number: 10665357
    Abstract: A nuclear steam supply system includes an elongated reactor vessel having an internal cavity with a central axis, a reactor core having nuclear fuel disposed within the internal cavity, and a steam generating vessel having at least one heat exchanger section, the steam generating vessel being fluidicly coupled to the reactor vessel. The reactor vessel includes a shell having an upper flange portion and a head having a head flange portion. The upper flange portion is coupled to the head flange portion, wherein the upper flange portion extends into the internal cavity, and the head flange portion extends outward from the internal cavity. The flanges have a space saving design which are configured to minimize outward extension from the cavity while still providing desired leak protection at the interface between the shell and the head.
    Type: Grant
    Filed: January 2, 2018
    Date of Patent: May 26, 2020
    Assignee: SMR INVENTEC, LLC
    Inventors: Krishna P. Singh, Joseph Rajkumar
  • Patent number: 8638900
    Abstract: An alignment plate that is attached to a core barrel of a pressurized water reactor and fits within slots within a top plate of a lower core shroud and upper core plate to maintain lateral alignment of the reactor internals. The alignment plate is connected to the core barrel through two vertically-spaced dowel pins that extend from the outside surface of the core barrel through a reinforcement pad and into corresponding holes in the alignment plate. Additionally, threaded fasteners are inserted around the perimeter of the reinforcement pad and into the alignment plate to further secure the alignment plate to the core barrel. A fillet weld also is deposited around the perimeter of the reinforcement pad. To accommodate thermal growth between the alignment plate and the core barrel, a gap is left above, below and at both sides of one of the dowel pins in the alignment plate holes through which the dowel pins pass.
    Type: Grant
    Filed: September 14, 2007
    Date of Patent: January 28, 2014
    Assignee: Westinghouse Electric Company LLC
    Inventors: David A. Altman, David R. Forsyth, Richard E. Smith, Norman R. Singleton
  • Patent number: 8596227
    Abstract: A steam generator with a heating gas duct which in an approximately horizontal heating gas direction is exposed to throughflow of a heating medium is provided to ensure a reliable absorption of the mentioned loads, especially of the additional loads which are produced as a result of the design dependent internal pressure of the heating gas. The heating gas duct is enclosed by a plurality of support frames which are arranged one behind the other in the heating gas direction, wherein at least two of the support frames are interconnected via a plurality of horizontal batten plates.
    Type: Grant
    Filed: August 1, 2008
    Date of Patent: December 3, 2013
    Assignee: Siemens Aktiengesellschaft
    Inventor: Fred Heinrichs
  • Publication number: 20130272485
    Abstract: A nuclear reactor vessel structure includes an inner peripheral tube-shaped steel plate, an outer peripheral tube-shaped steel plate, and an intermediate tube-shaped steel plate disposed between the inner and outer peripheral tube-shaped steel plates, and is configured to support a nuclear reactor vessel on the inner peripheral side of a tube-shaped structure with concrete placed between the steel plates. The nuclear reactor vessel structure includes a support having a tube-shaped plate disposed on the inner peripheral side of the intermediate tube-shaped steel plate, and an annular plate which protrudes to the inner peripheral side of the tube-shaped plate and to which a connection section is affixed. The support is affixed to the concrete, which is placed between the inner peripheral and the intermediate tube-shaped steel plates, by first bar members, and the support is also affixed to the inner peripheral tube-shaped steel plate by second bar members.
    Type: Application
    Filed: December 6, 2011
    Publication date: October 17, 2013
    Applicant: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Hiroshi Shimizu, Ryo Fujimoto, Kentaro Mori, Hiromu Okamoto, Hisashi Sekimoto, Hiroyuki Iseki
  • Patent number: 8355481
    Abstract: Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.
    Type: Grant
    Filed: August 14, 2009
    Date of Patent: January 15, 2013
    Assignee: GE-Hitachi Nuclear Energy Americas LLC
    Inventors: Michael R. Breach, David J. Keck, Gerald A. Deaver
  • Patent number: 8333170
    Abstract: A buckstay system is described comprising horizontal buckstays for the walls of a steam generator, for example in plural vertically space assemblies tied with vertical buckstays, in which a buckstay extends generally horizontally across each wall such as to form a connected pair with an adjacent buckstay at each corner; an elongate tie bar formation extends across each wall such as to form a fixedly mounted pair with an adjacent tie bar formation at each corner; an anchor assembly associated with each buckstay and providing engagement means by which each buckstay engages with a respective tie bar; and each horizontal buckstay is split to comprise at least two rigid elongate buckstay elements mounted together to be relatively slideable in a buckstay longitudinal direction.
    Type: Grant
    Filed: December 23, 2008
    Date of Patent: December 18, 2012
    Assignee: Doozan Babcock Energy America, LLC
    Inventor: Dewan Shamsuz Zaman
  • Publication number: 20120288054
    Abstract: To provide a lower foundation 30 provided on a ground 7 and an upper foundation 31 provided above the lower foundation 30 via a seismic isolator 32. A machine room S in which a machine K can be arranged is provided in the upper foundation 31. A foundation-side hull structure unit that is configured in a reticular pattern by horizontal reinforcing ribs extended in one direction and vertical reinforcing ribs extended to cross the horizontal reinforcing ribs is provided in the upper foundation 31, and the machine room S is provided in a space in the foundation separated by the horizontal reinforcing ribs and the vertical reinforcing ribs.
    Type: Application
    Filed: November 5, 2010
    Publication date: November 15, 2012
    Applicant: MITSUBISHI HEAVY INDUSTRIES, LTD.
    Inventors: Kunihiko Sato, Kenichi Sakurai
  • Patent number: 8170174
    Abstract: An embodiment of the present invention takes the form of an apparatus or system that may reduce the level of vibration experienced by an inlet riser or other similar object within a reactor pressure vessel. An embodiment of the present invention may eliminate the need for welding the riser brace to the inlet riser. An embodiment of the present invention provides at least one riser brace clamp that generally clamps the riser brace to the inlet riser. After installation, the riser brace clamp may lower the amplitude of, and/or change the frequency of, the vibration experienced by the inlet riser.
    Type: Grant
    Filed: June 11, 2009
    Date of Patent: May 1, 2012
    Assignee: GE-Hitachi Nuclear Energy Americas, LLC
    Inventors: Bruce J. Lentner, Michael S. DeFilippis
  • Patent number: 8107584
    Abstract: Example embodiment damping devices may include a housing capturing a piston. The housing may be filled and/or able to be filled with a damping fluid compatible with the nuclear reactor coolant, so that a leak from the housing or coolant passing into the housing does not damage the reactor or example embodiment devices. Example embodiments may further include one or more springs that provide an elastic force opposing movement between the piston and housing. A shaft of the piston and an end of the housing may be connected to two nuclear reactor components with relative motion or vibration to be damped. Example methods may use example embodiment damping devices to reduce and/or prevent relative motion and vibration among components of a nuclear reactor.
    Type: Grant
    Filed: May 6, 2008
    Date of Patent: January 31, 2012
    Assignee: GE-Hitachi Nuclear Energy Americas LLC
    Inventors: Michael S. Defilippis, James P. Carneal
  • Patent number: 8077824
    Abstract: A nuclear reactor includes a reactor pressure vessel 12 and a core barrel 14, contained within the reactor pressure vessel 12. The reactor 10 further includes a single vertical support 16, for transmitting vertical load from the core barrel to the reactor pressure vessel. Further, lateral support means is provided at an elevation which is above that of the support 16 to provide lateral support to the core barrel 14. This arrangement will result in reduced stress arising from the temperature fluctuations.
    Type: Grant
    Filed: May 27, 2004
    Date of Patent: December 13, 2011
    Assignee: Pebble Bed Modular Reactor (Proprietary) Limited
    Inventor: Fredrik Alfried Fortier
  • Publication number: 20110038450
    Abstract: Provided is a sliding support and a system using the sliding support unit. The sliding support unit may include a fulcrum capture configured to attach to a support flange, a fulcrum support configured to attach to the fulcrum capture, and a baseplate block configured to support the fulcrum support. The system using the sliding support unit may include a pressure vessel, a pedestal bracket, and a plurality of sliding support units.
    Type: Application
    Filed: August 14, 2009
    Publication date: February 17, 2011
    Inventors: Michael R. Breach, David J. Keck, Gerald A. Deaver
  • Patent number: 7822167
    Abstract: A technical installation, especially a nuclear power plant, has a number of system components that are respectively supported by a number of beams, and a number of pressurized conduits. The technical installation is designed in such a way that secondary damage occurring in the surroundings of pressurized conduits are kept particularly low even if the pressurized conduits rupture. This is achieved in that at least one of the beams is embodied in a segmented manner in an area that is expected to be affected if a pressurized conduit ruptures, adjacent segments preferably being connected to each other via screw connections.
    Type: Grant
    Filed: November 7, 2005
    Date of Patent: October 26, 2010
    Assignee: Areva NP GmbH
    Inventor: Wladimir Trubnikow
  • Patent number: 7685878
    Abstract: Two transducers to be rotated around a circumferential location on a cylindrical body for structural testing of the body are carried on a mounting and drive apparatus including a magnetic attachment which can be manually brought up to a pipe from one side only for fixed connection to the pipe on that side at a position axially spaced from a weld. A collar shaped support for the pair of transducers is formed of a row of separate segments which wrap around the pipe from the one side and is rotated around the axis of the pipe to carry the transducer around the circumferential weld. The segments carry rollers to roll on the surface and are held against the pipe by magnets. The transducers are carried on the support in fixed angular position to track their position but in a manner which allows slight axial or radial movement relative to the pipe.
    Type: Grant
    Filed: July 25, 2007
    Date of Patent: March 30, 2010
    Inventor: Randel Brandstrom
  • Patent number: 7668281
    Abstract: A method is provided for removing radioactive internals structural members in the core of a reactor pressure vessel in a containment vessel. The method includes placing a first cask in a first internals assembly, detaching radioactive first internals structural members from second internals structural members in the first internals assembly, placing the detached first internals structural members in the first cask, placing the first internals assembly in a second cask, and removing the second cask containing the first internals assembly and containing the casked detached radioactive first internals members from the containment vessel. The first internal members may be radioactive baffle plates, and the second internals members may be former plates bolted to the radioactive baffle plates. Novel tooling, framework and fixtures facilitate disassembling, moving and storing the radioactive baffle plates.
    Type: Grant
    Filed: January 17, 2007
    Date of Patent: February 23, 2010
    Assignee: Westinghouse Electric Co LLC
    Inventors: Leonard J. Balog, Thomas A. Hackley, Arthur W. Kramer
  • Publication number: 20090296877
    Abstract: An alignment plate that is attached to a core barrel of a pressurized water reactor and fits within slots within a top plate of a lower core shroud and upper core plate to maintain lateral alignment of the reactor internals. The alignment plate is connected to the core barrel through two vertically-spaced dowel pins that extend from the outside surface of the core barrel through a reinforcement pad and into corresponding holes in the alignment plate. Additionally, threaded fasteners are inserted around the perimeter of the reinforcement pad and into the alignment plate to further secure the alignment plate to the core barrel. A fillet weld also is deposited around the perimeter of the reinforcement pad. To accommodate thermal growth between the alignment plate and the core barrel, a gap is left above, below and at both sides of one of the dowel pins in the alignment plate holes through which the dowel pins pass.
    Type: Application
    Filed: September 14, 2007
    Publication date: December 3, 2009
    Inventors: David A. Altman, David R. Forsyth, Richard E. Smith, Norman R. Singleton
  • Patent number: 7627074
    Abstract: A vertical spring wedge restores a tight fitup against an adjacent structure, such as between an inlet mixer and an adjacent restrainer bracket in a boiling water nuclear reactor jet pump. The vertical spring wedge includes a U-shaped bracket including a pair of guiding portions and a pair of bracket holes. A pair of wedge assemblies are coupled with the bracket, each of the wedge assemblies including a wedge segment attached to a spring-loaded guide rod. The guide rods are displaceable in the bracket holes between a retracted position and an extended position. The wedge segments engage the guiding portions, and a combination of the bracket and wedge assemblies have a first width when the guide rods are in the retracted position and have a second width wider than the first width when the guide rods are in the extended position.
    Type: Grant
    Filed: October 24, 2006
    Date of Patent: December 1, 2009
    Assignee: General Electric Company
    Inventors: John Erbes, Thanh C. Tu, Mark William Broaddus
  • Patent number: 7596200
    Abstract: A clamp apparatus is provided which is designed to structurally replace a weld that attaches a riser brace assembly to a reactor pressure vessel wall, and a method for repairing the riser brace assembly. The riser brace assembly is designed to support a jet pump in the reactor pressure vessel. The riser brace assembly may include upper and lower riser brace leaves connected to a reactor pressure vessel pad on the wall. The clamp apparatus may include a first clamp component including a central extension portion, and a second clamp component including a slot portion. The central extension and slot portions may be engaged to provide alignment between the first and second clamp components between the upper and lower riser brace leaves of the riser brace assembly.
    Type: Grant
    Filed: March 28, 2005
    Date of Patent: September 29, 2009
    Assignee: General Electric Company
    Inventor: Grant Clark Jensen
  • Patent number: 7418072
    Abstract: A spacer for a fuel assembly for a light water nuclear reactor contains a plurality of intercrossed segments, which form a grid. The segments are formed from first and second metal strips which are assembled and provided with protruding parts or corrugations in such a way that the adjacent protruding parts are embodied in such a way that a flow component perpendicular to a vertical central plane which extends between the metal strips is applied to cold water running out from the flow sub-channel.
    Type: Grant
    Filed: May 12, 2005
    Date of Patent: August 26, 2008
    Assignee: Areva NP GmbH
    Inventors: Hans Kemner, Günter Bruch
  • Publication number: 20080198960
    Abstract: The reactor vessel of a nuclear reactor installation which is suspended from the cold leg nozzles in a reactor cavity is provided with a lower thermal insulating barrier spaced from the reactor vessel that has a hemispherical lower section that increases in volume from the center line of the reactor to the outer extent of the diameter of tiie thermal insulating barrier and smoothly transitions up the side walls of the vessel. The space between the thermal insulating harrier and the reactor vessel forms a chamber which can be flooded with cooling water through passive valving to directly cool the reactor vessel in the event of a severe accident. The passive inlet valve for the cooling water includes a buoyant door that is normally maintained sealed under its own weight and floats open when the cavity is Hooded. Passively opening steam vents are also provided.
    Type: Application
    Filed: May 3, 2007
    Publication date: August 21, 2008
    Inventors: C. Patrick Keegan, James H. Scobel, Richard F. Wright
  • Patent number: 7357100
    Abstract: A necessary size and number of modules each obtained by housing a member including heat exchanger tube panels each comprising a heat exchanger tube bundle and headers for the heat exchanger tube bundle, an upper casing of an exhaust heat recovery boiler (HRSG), provided above the heat exchanger tube panels, heat insulators, and heat exchanger tube panel support beams provided on the upper surface of the upper casing into a transportation frame, are prepared according to design specifications of the HRSG, and side casings and a bottom casing except for the ceiling part casing are constructed in advance at a construction site of the HRSG, and the modules are suspended from above between adjacent support beams of the ceiling part to dispose the heat exchanger tube panel support beams of the modules at the set heights of the ceiling part support beams, and the support beams and the ceiling part support beams are connected and fixed via connecting steel plates, whereby the respective modules are transported to the
    Type: Grant
    Filed: July 30, 2003
    Date of Patent: April 15, 2008
    Assignee: Babcock-Hitachi Kabushiki Kaisha
    Inventors: Isao Waseda, Atsuo Kawahara, Mitsugi Musashi, Toshinori Shigenaka
  • Patent number: 6813327
    Abstract: A core plate assembly for a nuclear reactor includes a plurality of support beams, a flat plate positioned on top of the support beams, a plurality of control rod guide tube openings arranged in staggered rows, and a plurality of fuel supports extending through the flat plate. Each guide tube opening has a cruciform shape defines four fuel bundle receiving areas. Each fuel support includes a coolant flow inlet, and a coolant flow outlet sized to receive a lower tie plate of a fuel bundle. The coolant flow inlet is offset from coolant flow outlet so that a centerline of the coolant flow inlet is parallel to a centerline of the coolant flow outlet. The coolant flow inlets are positioned adjacent a support beam, and the coolant flow outlets are positioned in a fuel bundle receiving area.
    Type: Grant
    Filed: October 19, 2000
    Date of Patent: November 2, 2004
    Assignee: General Electric Company
    Inventor: Roy C. Challberg
  • Patent number: 6594333
    Abstract: The present invention is used to reduce thermal load itself, being the cause to generate stress, which develops near liquid surface in a nuclear reactor wall and to contribute to further improvement of safety. A partition member (5) is arranged above a coolant liquid surface (9) in an annulus space (3) between a reactor vessel (1) and a guard vessel (2), a low-temperature gas is circulated through the annulus space above the partition member to cool down, the gas is circulated through the annulus space from under the coolant liquid surface to the partition member, and the high-temperature gas heated under the coolant liquid surface is used to raise the temperature above the coolant liquid surface.
    Type: Grant
    Filed: April 5, 2002
    Date of Patent: July 15, 2003
    Assignee: Japan Nuclear Cycle Development Institute
    Inventors: Naoto Kasahara, Masanori Ando
  • Patent number: 6570950
    Abstract: 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 cap to a support elevation for the component. A second inner steel concrete form can be employed to form an annular concrete channel through which the supports extend. The center of the inner form can be filled with a sand-like substance, radiation absorber material or concrete grout.
    Type: Grant
    Filed: March 11, 2002
    Date of Patent: May 27, 2003
    Assignee: Westinghouse Electric Company LLC
    Inventor: Donn Moore Matteson
  • Patent number: 6520123
    Abstract: An open-webbed cage support device providing support that enabling a mechanical device such as a thermal expansion tank to be suspended or mounted adjacent to the thermal water heating device without the need to improvise a “made in the field” support structure.
    Type: Grant
    Filed: July 19, 2001
    Date of Patent: February 18, 2003
    Inventors: Philip A. Parker, Patricia E. Garvin
  • Patent number: 6389094
    Abstract: A forged upper shroud section which may be machined from a single piece rectangular cross-section ring forging and includes a circular flange and a cylindrical shell is described. Openings and slots are machined into the flange to align and support the shroud head. A groove is machined along an inside surface of the cylinder section, and the groove may be used to support top guide grid (not shown). An end of the cylinder section is machined with a weld prep for attachment to the core section of the shroud.
    Type: Grant
    Filed: February 2, 1998
    Date of Patent: May 14, 2002
    Assignee: General Electric Company
    Inventors: Jack T. Matsumoto, Alex B. Fife
  • Patent number: 6351510
    Abstract: A nuclear power plant comprising a casing which encloses a primary space, a reactor vessel arranged in the primary space, and a reactor core provided in the reactor vessel. The plant further comprises an upper space provided above the casing. The reactor core is separated from the upper space by means of an openable cover arrangement. The casing is designed in such a manner that the primary space is completely closed against the environment to at least the level corresponding to the most highly located part of the reactor core. The upper space is arranged to house a volume of a liquid sufficiently large to permit the filling of the primary space with the liquid to a level located above the most highly located part of the reactor core.
    Type: Grant
    Filed: September 14, 1999
    Date of Patent: February 26, 2002
    Assignee: ABB Atom AB
    Inventors: Ulf Bredolt, Johan Engström, Bengt Ivung
  • Publication number: 20010026605
    Abstract: 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 chamber for covering the aperture portion can be performed independent of other work performed in the reactor building, before at least a part of work of using a roof crane and at least a part work of handling fuel assemblies in the reactor building.
    Type: Application
    Filed: March 15, 2001
    Publication date: October 4, 2001
    Inventors: Masataka Aoki, Takahiro Adachi
  • Patent number: 6233301
    Abstract: An electrode discharge machining (EDM) apparatus for machining slots in a jet pump diffuser in a nuclear reactor pressure vessel is described. The apparatus is configured to machine a plurality of slots in the diffuser at positions behind the diffuser sensing line within the plane formed by the center of the diffuser and the sensing line. The apparatus includes a housing, a plurality of clamp assemblies, a hook assembly configured to engage the sensing line standoff so that the apparatus is positioned at an angle from a plane formed by the center of the diffuser and the sensing line, and a plurality of electrode assemblies. The EDM apparatus can be configured to be installed clockwise or counter-clockwise around the sensing line depending on the spacing available around given diffusers. The EDM apparatus is capable of burning a plurality of slots at the same time, thereby saving time and money.
    Type: Grant
    Filed: September 25, 1998
    Date of Patent: May 15, 2001
    Assignee: General electric Company
    Inventor: Merlene Robergeau
  • Patent number: 6173027
    Abstract: A primary containment vessel comprises an outer peripheral concrete wall surrounding a reactor pressure vessel, a pipe arrangement of a reactor water recirculation system and other reactor systems and equipments, a mat concrete wall positioned below the outer peripheral concrete wall, a reactor pressure vessel (RPV) pedestal supporting the reactor pressure vessel, a horizontal wall joining the outer peripheral concrete wall and the RPV pedestal, upper and lower dry wells, a wet well having a suppression pool in which water is stored, an isolation member for air-tightly isolating the upper dry well and the lower dry well at a position supporting the reactor pressure vessel, vent pipe arrangement used for the upper dry well communicating the upper dry well with the suppression pool, a high pressure gas inflow member used for the upper dry well located in a communicating hole formed to the RPV pedestal so as to communicate the vent pipe used for the upper dry well with a gas phase section of the wet well, anothe
    Type: Grant
    Filed: March 31, 1999
    Date of Patent: January 9, 2001
    Assignee: Kabushiki Kaisha Toshiba
    Inventors: Takashi Saito, Akiro Asano, Shuji Hirono
  • Patent number: 6160864
    Abstract: A seismic load suppressing system for a nuclear reactor that reduces the seismic input to the reactor and the internal components of the reactor including the fuel is described. The seismic load suppressing system includes, in one embodiment, a plurality of seismic isolators positioned circumferentially between the reactor pedestal and a lower pedestal and a plurality of displacement limiters coupled to a lower pedestal skirt and positioned adjacent the reactor pedestal. The seismic isolators include a plurality of alternating layers of a resilient material and steel plates bonded together. Each displacement limiter includes a cantilever beam. The beam includes a beam core and two steel plates laminated on opposing outer surfaces of the beam core. The steel plates are fabricated from carbon steel having a lower yield strength than the beam core.
    Type: Grant
    Filed: March 5, 1999
    Date of Patent: December 12, 2000
    Assignee: General Electric Company
    Inventors: Perng-Fei Gou, Enrique Rafael Solorzano, Giancarlo Barbanti
  • Patent number: 6091791
    Abstract: A shroud attachment assembly which provides both structural support for the shroud and a seal between the shroud and shroud support is described. In one specific embodiment, the shroud attachment assembly includes a shroud flange formed integral with the shroud, and a pump deck flange formed integral with the pump deck. The shroud flange extends over the pump deck flange, and a plurality of studs extend through aligned openings in the flanges. In addition, a plurality of wedges are secured to the shroud flange by studs, and the wedges extend between the shroud flange and the pump deck flange. Generally, the studs which extend through aligned openings in the shroud and pump deck flanges transfer vertical loads from the shroud to the pump deck, and the wedges transfer horizontal loads from the shroud to the pump deck.
    Type: Grant
    Filed: February 2, 1998
    Date of Patent: July 18, 2000
    Assignee: General Electric Company
    Inventors: Jack T. Matsumoto, Alex B. Fife
  • Patent number: 6021170
    Abstract: A nuclear reactor plant includes a reactor pressure vessel having a core barrel supported on a cylindrical holding structure fixed in the reactor pressure vessel. The core barrel has a lower part with at least one elastically resilient segment. A projection disposed on the segment engages under the holding structure in such a way that a wedge-like gap is formed between a lower surface of the holding structure and the projection. A wedge is braced in the gap. A method is also provided for mounting the core barrel.
    Type: Grant
    Filed: September 11, 1998
    Date of Patent: February 1, 2000
    Assignee: Siemens Aktiengesellschaft
    Inventors: Gerd Reimer, Herbert Schramm
  • Patent number: 6009137
    Abstract: A mid-shroud joint which improves the replaceability of the shroud is described. In one embodiment, the shroud includes a core shroud and a lower shroud. A core plate support flange is clamped between the core shroud and the lower shroud, and the core plate support flange supports a core plate. The mid-shroud joint is formed by a flange of the core shroud and a flange of the lower shroud. The core plate support flange is positioned between core shroud and lower shroud flanges, and openings in these flanges align so that bolts can be inserted through such aligned openings.
    Type: Grant
    Filed: February 2, 1998
    Date of Patent: December 28, 1999
    Assignee: General Electric Company
    Inventors: Jack T. Matsumoto, Alex Fife
  • Patent number: 5930320
    Abstract: Support assemblies for allowing RPV radial expansion while simultaneously limiting horizontal, vertical, and azimuthal movement of the RPV within a nuclear reactor are described. In one embodiment, the support assembly includes a support block and a guide block. The support block includes a first portion and a second portion, and the first portion is rigidly coupled to the RPV adjacent the first portion. The guide block is rigidly coupled to a reactor pressure vessel support structure and includes a channel sized to receive the second portion of the support block. The second portion of the support block is positioned in the guide block channel to movably couple the guide block to the support block.
    Type: Grant
    Filed: January 27, 1998
    Date of Patent: July 27, 1999
    Assignee: General Electric Company
    Inventors: Roy C. Challberg, Perng-Fei Gou, Cherk Lam Chu, Robert P. Oliver
  • Patent number: 5864594
    Abstract: An apparatus and method are provided for replacing the existing lower internal components in a nuclear reactor vessel with new components. The alignment of the new lower internals to the pressure vessel and the existing upper internals is achieved by customizing the new lower internals on-site based on alignment measurements obtained by gages installed on the new core barrel and the existing upper core plate. The gages allow the custom machining of radial support keys on the lower portion of the new core barrel and the custom drilling of upper core plate alignment pin holes in the new core barrel.
    Type: Grant
    Filed: August 2, 1996
    Date of Patent: January 26, 1999
    Assignee: Westinghouse Electric Corporation
    Inventors: Leonard J. Balog, Bruce W. Bevilacqua, Ronald J. Hopkins, Arthur W. Kramer, Donald G. Sherwood
  • Patent number: 5802129
    Abstract: In a pressure vessel of a nuclear reactor containing a core assembly enclosed within a core shroud, the core shroud spaced radially inwardly of a pressure vessel wall, with an annular shroud support plate fixed to the pressure vessel wall, wherein a lower end of the shroud is seated on an upper edge of the support plate to create a joint interface further wherein, and a plurality of brackets are secured between the shroud and the shroud support plate, spanning the joint interface.
    Type: Grant
    Filed: January 11, 1996
    Date of Patent: September 1, 1998
    Assignee: General Electric Company
    Inventors: Gerald A. Deaver, Barry H. Koepke
  • Patent number: 5781603
    Abstract: In order to support a shroud against bending, shear, stress and torsion, straps which are preferably formed of the same material as the shroud, are placed in strategic positions with respect to cracks or the like type of weaknesses which have been detected, and fastened in place using a suitable fastening technique. In the preferred embodiments of the invention holes are formed using an EDM technique and bolt units which have an expanding portion are inserted into the holes, torqued and expanded in a manner which fastens the strap to the shroud. Welding and the like type of fastening techniques are not excluded and may used alternatively or in combination with the bolting technique as required.
    Type: Grant
    Filed: January 17, 1997
    Date of Patent: July 14, 1998
    Assignee: Combustion Engineering, Inc.
    Inventor: Adrian Peter Wivagg
  • Patent number: 5746540
    Abstract: A method of entombing a nuclear reactor where the reactor with its bio-shield remains intact. An access shaft, several lateral adits, and several chambers below the reactor location are excavated to provide access at underground locations below the reactor. A main cavern is excavated and lined with a lower base, surrounding sidewall, and a roof structure which has thermal plate at its lower surface. Freeze/thaw pipes are erected vertically in the cavern, and these extend through the earth strata below the cavern into a lower operating chamber. The cavern is filled with water which is then frozen, and the earth strata immediately below the reactor and are isolated from the surrounding earth strata and structure. The upper surface of the ice block is melted by the thermal plate in a controlled manner to lower the reactor, after which concrete and other material is used to fill all of the man made cavities and thus entomb the reactor.
    Type: Grant
    Filed: May 6, 1996
    Date of Patent: May 5, 1998
    Inventors: David J. Hindle, Christopher D. Breeds, Jeremy J. Conway, Ian W. Morris, Eric Ledgerwood
  • Patent number: 5740216
    Abstract: A vertical seismic isolation structure is capable of achieving vertical seismic isolation of nuclear reactor components connected to each other by primary pipings, while suppressing the relative displacement with respect to the primary pipings. A nuclear reactor vessel, circulating pumps and heat exchangers, all of which are connected to each other by primary pipings in which a coolant is circulated, are mounted on a common deck. Vertical seismic isolators each of which has laminated large coned disc springs and is capable of expanding and contracting in only the vertical direction are installed on the top of a concrete wall surrounding the respective nuclear reactor components. The common deck is placed on all the vertical seismic isolators so as to support the entire seismic isolation structure (the common deck, the nuclear reactor components, etc.).
    Type: Grant
    Filed: August 30, 1995
    Date of Patent: April 14, 1998
    Assignee: Doryokuro Kakunenryo Kaihatsu Jigyodan
    Inventor: Masaki Morishita
  • Patent number: 5640434
    Abstract: The present invention relates to a miniaturized nuclear utilizing improved pressure tube structural members. More particularly, the present invention relates to a new miniaturized nuclear reactor utilizing novel structural members that are used to support the loads and stresses of multiple nuclear reactor fuel channel pressure tubes and calandria tubes in a moderator.
    Type: Grant
    Filed: July 31, 1995
    Date of Patent: June 17, 1997
    Inventor: Sigmunt Rottenberg
  • Patent number: 5610962
    Abstract: A nuclear power generation complex constructed on a stratum of rock overlain by soil deposits. All major structures in the power generation complex (i.e., reactor, turbine, radwaste and control buildings) are located on a common mat foundation that houses elastomeric bearings or seismic isolators. The foundation includes a concrete slab supported by a plurality of pedestals. Each of the pedestals is embedded in the rock. Preferably, each pedestal is a circular metal shell filled with underwater-type concrete, and the concrete slab is reinforced with steel bars. For example, a reactor building is supported by one set of seismic isolators mounted on the concrete slab, and a turbine building is supported by another set of seismic isolators mounted on the concrete slab. The isolators filter out a great deal of the seismic vibratory inputs. The common mat foundation eliminates differential movements between the buildings.
    Type: Grant
    Filed: September 22, 1995
    Date of Patent: March 11, 1997
    Assignee: General Electric Company
    Inventors: Enrique R. Solorzano, Perng-Fei Gou, Thomas S. Higa, Harold E. Townsend
  • Patent number: 5608767
    Abstract: A device for generating direct current by neutron activation of a plurality of series-connected beta-emitter (nuclear decay electron) cells, located in the out-of-core region of a light water nuclear reactor. The device can be used as either a current source, or preferably configured as a DC voltage source, capable of powering low-power, radiation-hardened, high-temperature integrated circuitry contained in the reactor vessel. As such, the device acts like a DC battery that is activated by (n, .gamma.) reactions, both thermal and epithermal (by resonance capture). The device is not operable until exposed to a substantial neutron flux, so it has unlimited shelf-life and is not radioactive during manufacture In the preferred embodiment, an isotope of the metallic rare-earth element dysprosium is configured in a "sandwich" geometry to generate sufficient current that a useful steady voltage can be generated by means of a simple voltage regulation circuit.
    Type: Grant
    Filed: July 21, 1995
    Date of Patent: March 4, 1997
    Assignee: General Electric Company
    Inventors: James H. Terhune, Robert L. Cowan, II
  • Patent number: 5574760
    Abstract: In order to eliminate the need to weld, drill or otherwise machine a shroud structure which is used to surround a plurality of fuel assemblies in a nuclear reactor, a plurality of upper hanger rods interconnect a structure above the shroud to a support ring which is clamped about the upper periphery of the shroud. Lower hanger rods interconnect a lower edge or shoulder portion of the shroud with the support ring. Thus, through the upper and lower hanger rods and the support ring, the shroud can be supported within the RPV. The upper support ring is arranged to clamp the lower ends of the upper hanger rods against the upper outer peripheral portion of the shroud while the lower ends of the lower hanger rods are clamped against the lower peripheral wall portion of the shroud by a lower support ring.
    Type: Grant
    Filed: November 8, 1995
    Date of Patent: November 12, 1996
    Assignee: Combustion Engineering, Inc.
    Inventor: Bengt I. Baversten
  • Patent number: 5550883
    Abstract: The vessel of the nuclear reactor includes at least three assemblies (22) distributed around the periphery of the core support plate (25), each comprising a key (26) fixed to the inner surface of the wall (21) of the vessel at the core support plate (25) and a cut-out (29) in the external edge of the core support plate (25) and open towards the outside in order to receive, with a clearance, an end part (30) of the key (26). The cut-out (29) includes an upper surface (29d) perpendicular to the axis of the wall (21) of the vessel and of the lower internals (23), which is machined in the core support plate (25) in order to retain the internals (23) in the event of a drop. A keyhole slot (28) is fixed inside the cut-out (29). In order to carry out the adjustment of the dimensions of the keyhole slot (28), a standard keyhole slot may be used, equipped with distance measurement sensors in order to obtain the desired clearances between the key (26) and the keyhole slot (28).
    Type: Grant
    Filed: March 15, 1995
    Date of Patent: August 27, 1996
    Assignee: Framatome
    Inventor: Jean-Claude Bougis
  • Patent number: 5488643
    Abstract: In order to eliminate the need to weld, drill or otherwise machine a shroud structure which is used to surround a plurality of fuel assemblies in a nuclear reactor, a plurality of upper hanger rods interconnect a structure above the shroud to a support ring which is clamped about the upper periphery of the shroud. Lower hanger rods interconnect a lower edge or shoulder portion of the shroud with the support ring. Thus, through the upper and lower hanger rods and the support ring, the shroud can be supported within the RPV. The upper support ring is arranged to clamp the lower ends of the upper hanger rods against the upper outer peripheral portion of the shroud while the lower ends of the lower hanger rods are clamped against the lower peripheral wall portion of the shroud by a lower support ring.
    Type: Grant
    Filed: May 11, 1994
    Date of Patent: January 30, 1996
    Assignee: Combustion Engineering, Inc.
    Inventor: Bengt I. Baversten
  • Patent number: 5430779
    Abstract: In order to eliminate the need to weld, drill or otherwise machine a shroud structure which is used to surround a plurality of fuel assemblies in a nuclear reactor, a support ring which either seats on top of the upper edge of the shroud, or is formed in multiple segments and is clamped to the side wall of the shroud, have hangers which are rigid therewith on which support hooks can be detachably mounted. The hooks are arranged to be engagable with the inner peripheral wall of the RPV in a manner which prevents lateral movement of the shroud within the pressure vessel.
    Type: Grant
    Filed: May 16, 1994
    Date of Patent: July 4, 1995
    Assignee: Combustion Engineering, Inc.
    Inventors: Bengt. I. Baversten, Adrian P. Wivagg
  • Patent number: 5379331
    Abstract: An adjusting and positioning assembly for a bearing element (55), constituted by a nut (52) carried by a base plate, (40) fixed on a wall of a concrete structure in which the component is arranged, and a screw-jack (54) engaged with and blockable with respect to the nut (52). The transverse holding of the lower part of a steam generator pressurized-water nuclear reactor is provided by an assembly of supports each constituted by an adjustable transverse holding device (24) according to the invention. The position of the bearing element is adjusted in such a manner as to maintain play allowing movement of the steam generator as a result of thermal effects or in the event of an earthquake.
    Type: Grant
    Filed: March 24, 1993
    Date of Patent: January 3, 1995
    Assignee: Framatome
    Inventor: Serge Brouttelande
  • Patent number: 5301212
    Abstract: The irradiated component (1) comprises at least one tubular wall with its axis vertical and fastened inside a well (2) in a concrete structure (3). The connecting elements between the concrete structure (3) and the component (1) are destroyed, the component (1) is displaced in successive steps in the vertical direction along its axis on the inside of the well (2), and the wall of the component is cut, so as to obtain blocks (26) of irradiated material of the wall, at the upper level of the well (2) of the concrete structure (3) after each displacement of the component (1). The cut blocks (26) are disposed of for the purpose of elimination or storage. The displacement of the component can be obtained by a pull or push on its lower bottom.
    Type: Grant
    Filed: November 17, 1992
    Date of Patent: April 5, 1994
    Assignee: Framatome
    Inventors: Paul Jacquier, Jean-Paul Guigon
  • Patent number: 5278880
    Abstract: A pressurizer tank in a pressurized water nuclear reactor is mounted between structural walls of the reactor on a substructure of the reactor, the tank extending upwardly from the substructure. For bearing lateral loads such as seismic shocks, a girder substantially encircles the pressurizer tank at a space above the substructure and is coupled to the structural walls via opposed sway struts. Each sway strut is attached at one end to the girder and at an opposite end to one of the structural walls, and the sway struts are oriented substantially horizontally in pairs aligned substantially along tangents to the wall of the circular tank. Preferably, eight sway struts attach to the girder at 90.degree. intervals. A compartment encloses the pressurizer tank and forms the structural wall. The sway struts attach to corners of the compartment for maximum stiffness and load bearing capacity.
    Type: Grant
    Filed: June 24, 1992
    Date of Patent: January 11, 1994
    Assignee: Westinghouse Electric Corp.
    Inventors: Tod H. Baker, Howard L. Ott
  • Patent number: 5268944
    Abstract: A nuclear reactor is provided having a generally cylindrical reactor vessel disposed within an opening in a primary shield. The opening in the primary shield is defined by a plurality of generally planar side walls forming a generally polyhedral-shaped opening. The reactor vessel is supported within the opening in the primary shield by reactor vessel supports which are in communication and aligned with central portions of some of the side walls. The reactor vessel is connected to the central portions of the reactor vessel supports. A thermal insulation polyhedron formed from a plurality of slidably insertable and removable generally planar insulation panels substantially surrounds at least a portion of the reactor vessel and is disposed between the reactor vessel and the side walls of the primary shield. The shape of the insulation polyhedron generally corresponds to the shape of the opening in the primary shield.
    Type: Grant
    Filed: June 24, 1992
    Date of Patent: December 7, 1993
    Assignee: Westinghouse Electric Corp.
    Inventors: Douglas E. Ekeroth, Richard Orr