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HANDLING OF FISSION REACTOR COMPONENT STRUCTURE WITHIN REACTOR SYSTEM

Subclass of:

376 - Induced nuclear reactions: processes, systems, and elements

Patent class list (only not empty are listed)

Deeper subclasses:

Class / Patent application numberDescriptionNumber of patent applications / Date published
376272000 Storage container systems for new and/or irradiated core elements 46
376261000 Fuel component 40
376268000 Refueling machines 4
20090161811REFUELING SUPPORT SYSTEM - Problem: To provide a refueling support system in which fuel transfer procedure establishing operations and associated operations precisely reflecting the fuel burnup conditions can be efficiently performed at the time of scheduled outages at a nuclear power plant.06-25-2009
20080205577Systems for aligning and handling fuel rods within a nuclear fuel bundle - In a spent fuel pool of a nuclear power plant, there is provided a system for aligning a nuclear fuel bundle and handling selected fuel rods within the fuel bundle. The bundle includes water rods, full-length and part-length fuel rods extending through a plurality of fuel spacers provided between top and bottom ends of the bundle, each spacer having a plurality of cells accommodating corresponding fuel and water rods. The system includes a bundle alignment system for aligning the fuel rods and water rods, a rod grapple tool to extract selected part-length rods from the bundle, and a fuel rod guide block slidable onto the top end of the bundle for protecting an uppermost fuel spacer of the bundle, and for aligning fuel rods within individual cells of all the fuel spacers in the fuel bundle08-28-2008
20090060111CHANNEL SEATING TOOL FOR NUCLEAR FUEL ASSEMBLY AND METHOD FOR SEATING CHANNEL ON THE ASSEMBLY - A tool to slide a channel on a nuclear reactor fuel bundle assembly, the tool includes: a plate having a slot to receive a handle of the fuel bundle and a lower surface that engages an upper edge of the channel; at least one post extends up from the plate, and an arm is attached to a pivot on the post and includes a first end to receive a downward force and a second end adapted to engage the handle of the fuel bundle to apply an upward force to the handle and push down on the channel.03-05-2009
20100232564SYSTEMS FOR ALIGNING AND HANDLING FUEL RODS WITHIN A NUCLEAR FUEL BUNDLE - In a spent fuel pool of a nuclear power plant, there is provided a system for aligning a nuclear fuel bundle and handling selected fuel rods within the fuel bundle. The bundle includes water rods, full-length and part-length fuel rods extending through a plurality of fuel spacers provided between top and bottom ends of the bundle, each spacer having a plurality of cells accommodating corresponding fuel and water rods. The system includes a bundle alignment system for aligning the fuel rods and water rods, a rod grapple tool to extract selected part-length rods from the bundle, and a fuel rod guide block slidable onto the top end of the bundle for protecting an uppermost fuel spacer of the bundle, and for aligning fuel rods within individual cells of all the fuel spacers in the fuel bundle.09-16-2010
Entries
DocumentTitleDate
20110280359SELF LOCKING MAST ASSEMBLY AND METHOD OF MAKING - A mast arrangement having two elongate individual masts. The first elongate individual mast comprises a hollow connector comprising an inner diameter. The second elongate individual mast comprises a protruding connector end. The protruding connector end telescopically engages with the hollow connector end. The mast arrangement also comprises a pin and slot arrangement and collars to connect the masts together and minimize unwanted disengagement of the masts from each other.11-17-2011
20100046691METHOD FOR DISMANTLING A CONTROL ELEMENT OF A BOILING WATER REACTOR - A method enables dismantling of a control element of a boiling water reactor. Two control element leaves that are disposed opposite one another are separated by means of a roll-cutting method from the other two control element leaves, respectively along an intersection line extending in the longitudinal direction thereof and in the vicinity of the longitudinal center axis.02-25-2010
20090135985MAINTENANCE AND REPAIR DEVICE FOR STRUCTURE INSIDE NUCLEAR REACTOR - A maintenance/repair device for reactor internal structure 05-28-2009
20090285345METHOD AND TOOLING FOR DISMANTLING, CASKING AND REMOVAL OF NUCLEAR REACTOR CORE STRUCTURES - 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 of 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.11-19-2009
20130070884MAINTENANCE AND REPAIR DEVICE FOR STRUCTURE INSIDE NUCLEAR REACTOR - A maintenance/repair device for reactor internal structure 03-21-2013
20120224663NUCLEAR STEAM GENERATOR SUPPORT AND ALIGNMENT STRUCTURE - A nuclear steam generator support and alignment system that supports the entire weight of a nuclear steam generator on the walls of the shielding compartment in which the steam generator is designed to operate within. The support includes hydraulic positioners that can raise, lower, rotate and tilt the steam generator to align the steam generator with reactor coolant piping to which it is to be connected.09-06-2012
20090245451MOBILE RIGGING STRUCTURE - A U-framed structure that spans a reactor vessel of a pressurized water reactor power plant and rides on wheels that fit on the rails of the nuclear plant's refueling machine. A curved monorail is supported on the underside of the U-frame structure and guides a trolley system which travels on the monorail. The trolley system supports a hoist which is used for lifting, positioning and lowering reactor service equipment on the floor of the power plant's refueling canal.10-01-2009
20100002825AUTOMATIC CONNECTION DEVICE AND METHOD FOR REMOTELY CONNECTING THE DUCTS FOR GUIDING A THERMOCOUPLE FOR THE UPPER INTERNALS OF A NUCLEAR REACTOR - The invention relates to a device for connecting the upper (01-07-2010
20110299648CONTROL ROD DRIVE SHAFT UNLATCHING TOOL - 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.12-08-2011
20120099692SUBMERSIBLE MACHINE STRUCTURED TO CARRY A TOOL TO A LIMITED ACCESS LOCATION WITHIN A NUCLEAR CONTAINMENT - A tool for delivery of a testing element to a limited access location within a nuclear containment includes a rotation apparatus having a connection element that is configured to have an aperture that is formed generally centrally therein. A submersible machine is structured to carry the tool to a limited access location within a nuclear containment. The submersible machine includes a mount apparatus configured to be movably clamped onto a steam dam of a nuclear reactor apparatus and to drive the submersible machine circumferentially along the steam dam to inspect a plurality of jet pumps or other limited access locations of the nuclear reactor apparatus. The improved submersible machine advantageously further includes an adjustment table between the mount apparatus and a frame that carries the tool to enable rapid accurate positioning of the frame, and thus the tool, once the submersible machine has been mounted to the steam dam.04-26-2012
20120236978TOOL FOR DELIVERY OF TESTING ELEMENT TO A LIMITED ACCESS LOCATION WITHIN A NUCLEAR CONTAINMENT - An improved tool for delivery of a testing element to a limited access location within a nuclear containment includes a rotation apparatus having a connection element that is configured to have an aperture that is formed generally centrally therein. The aperture is structured to receive therein a cable that extends from a testing element, which that avoids the need to use slip rings or similar devices to permit the testing element to carried on a pivotable and rotatable structure. Moreover, an improved submersible machine is structured to carry the tool to a limited access location within a nuclear containment.09-20-2012
20100034334Pressuriser for a Pressurised Water Nuclear Power Plant - 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.02-11-2010
20090279656Apparatuses and methods for damping nuclear reactor components - 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.11-12-2009
20100002826BOLT FIXING DEVICE OF JET PUMP BEAM - A jet pump is provided with a riser as a coolant supply tube, an inlet mixer forming a turn-around path for the coolant, a diffuser and a jet pump beam provided with a bolt fixing device. The bolt fixing device includes: a head bolt of a jet pump beam for pushing and supporting the inlet mixer from an upper side of the riser, the head bolt being provided with a polygonal head portion; a lock cap provided on the polygonal head portion of the head bolt to be slidable in an axial direction thereof and integrally rotatable; a body housing disposed on an upper surface of the jet pump beam and adapted to accommodate the lock pin; a plurality of tapered external teeth formed on an outer peripheral side surface of the lock cap; and a plurality of internal tooth-shaped grooves formed to the body housing so as to be selectively engaged with the external teeth of the lock cap so as to fix the head bolt of the jet pump beam.01-07-2010
20120294405PRESSURIZED WATER REACTOR WITH UPPER VESSEL SECTION PROVIDING BOTH PRESSURE AND FLOW CONTROL - 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.11-22-2012
20110007861Machinery system allowing replacement of old reactor with a new reactor in nuclear power electric generating station - The machinery system and its application herewith, intended to create an opening in the roof of a Reactor Primary Containment of Generation II and III Nuclear Power Electric Generating Station. This opening is necessary to replace an aging nuclear reactor with a new, safer and more efficient reactor. Generation II and III Nuclear Power Electric Generating Stations include General Electric (GE) Boiling Water Reactor BWR/2, 3, 4, 5 and BWR/6 located in Mark II, and Mark III wet containments and Pressurized Water Reactors manufactured by Westinghouse, Combustion Engineering and Babcock and Wilcox located in dry containments. Until this time, existing reactor replacement was not possible due to Reactor Primary Containment structural enclosure configuration. The Dual Head Vertical Milling Machine System will remove a Reactor Primary Containment Dome Segment thus providing an opening, allowing reactor replacement and the electric generating station to remain operational for an other 40 years and beyond. Original containment integrity will be reinstated by closure of the opening.01-13-2011
20110142187METHOD FOR REMOVING THERMAL SLEEVE FROM COLD LEG OF REACTOR COOLANT SYSTEM - Disclosed is a method for removing a thermal sleeve from a cold leg of a reactor coolant system, which enables removal of an unintentionally separated thermal sleeve without implementation of a pipe cutting operation, preventing invasion of impurities into pipes and securing reliability in repetitious welding of the pipes. In particular, the method enables a remote operation and an underwater operation using wire ropes, thus being capable of minimizing a negative effect on workers due to radiation exposure.06-16-2011
20110142188APPARATUS FOR REMOVING THERMAL SLEEVE FROM COLD LEG OF REACTOR COOLANT SYSTEM - Disclosed is an apparatus for removing a thermal sleeve from a cold leg of a reactor coolant system, which removes an unintentionally separated thermal sleeve without pipe cutting, preventing invasion of impurities into pipes and achieving reliable pipe re-welding. The apparatus includes a sleeve removal tool including a corn head formed at a shaft, a pressure plate below the corn head to maximize hydraulic pressure inside a safety injection pipe, a spring connected to the pressure plate to keep the pressure plate unfolded, and a guide wheel to guide the sleeve removal tool into the safety injection pipe, a horizontal movement carrier including bodies connected to each other by a link, a seating rod for seating of the sleeve removal tool, and moving wheels for movement of the horizontal movement carrier, and a vertical movement carrier including first and second anti-separation bars to prevent separation of the horizontal movement carrier.06-16-2011
20100014622Nut assembly for handling poles and method thereof - An apparatus and method for manufacturing a handling pole including a pole section, a pole adapter connected to one end of the pole section, a spade member connected to the other end of the pole section, and a nut assembly for connecting adjoining poles. The pole adapter may include an upper sleeve and the spade member may include a lower sleeve.01-21-2010
20090116606JOINT TONG APPARATUS FOR RADIATION SHIELDING FACILITY - A joint tong apparatus for a radiation shielding facility. A spherical ball has a through-hole. An inner spherical socket and an outer spherical socket are installed in a hole formed in a partition between a radiation-shielded room and a control room so as to enclose the spherical ball on inner and outer sides. A bar is inserted and coupled into and to the through-hole of the spherical ball. An inner joint assembly has a first housing coupled to a shielded room-side end of the bar and a first pivot member pivotably mounted on a free end of the first housing. An outer joint assembly having a second housing coupled to a control room-side end of the bar and a second pivot member pivotably mounted on a free end of the second housing. The apparatus further includes a tong assembly, a handle assembly, a tong manipulation cable, and a pair of pivot manipulation cables.05-07-2009
20100150296PREVENTIVE MAINTENANCE/REPAIR DEVICE AND PREVENTIVE MAINTENANCE/REPAIR METHOD FOR CYLINDRICAL STRUCTURE - A preventive maintenance/repair device 06-17-2010
20110235769CONTROL ROD TRANSFER DEVICE - A telescoping rod control cluster assembly change tool for moving control rod assemblies among fuel assemblies in a nuclear facility. The operation of the tool is completely mechanical and the telescoping feature enables the tool to have a relatively low profile when it is being moved and stored without housing a control rod assembly. Rigidly supported alignment cards guide a gripper that attaches to the control rod assembly as the control rod assembly is withdrawn into the tool with the alignment cards preventing any lateral or rotational movement of the gripper.09-29-2011
20090323883Method For Carrying Out Reactor Internal - A method for carrying out a reactor internal, comprising steps of: 12-31-2009
20090067564System For Exchanging A Control Rod Drive - A system for exchanging a control rod drive of a nuclear reactor is provided. The system may include an integrated drive exchange assembly system (IDEAS). The IDEAS may include a trunnion cart attached to a tower assembly. The tower assembly may include an integrated extension carriage assembly.03-12-2009
20110026662Instrument Removal System - An instrument removal system for removing detector cables from a nuclear reactor includes a removal cart and a disposal cask. in an exemplary embodiment, the removal cart includes a base including a plurality of wheels coupled thereto, a motor mounted on the base, and a drive shaft operatively coupled to the motor. A disposal spool is removably mounted on the drive shaft, and the disposal spool includes a notch sized to receive the detector cable. A housing is mounted on the base, with the housing enclosing the disposal spool. Also, an entrance port is located in the housing to permit the detector cable to enter the housing.02-03-2011
20090323882Method for providing a dry environment for underwater repair of the reactor bottom head using a segmented caisson - Welding repairs are performed in an underwater environment adjacent the bottom head of the nuclear reactor vessel. To provide a dry welding environment, segments of a lower caisson are passed through the core plate holes and assembled along the interior surface of the bottom head. The assembled segments are held down by brackets and sealed to one another and to the bottom head by a water curable polymer. An upper caisson is passed through the core plate hole to sealingly engage the lower caisson. The caissons are pumped dry and welding equipment is passed through the caissons to effect weld repairs about the stub tube or along the bottom head cladding.12-31-2009
20110096889INDEXING DEVICE INSTALLATION UNIT - Maintainability of a traversing in-core probe is improved without any hindrance to passage and the like in an access tunnel in which an indexing device of a TIP system is installed. An indexing device installation unit provided in the TIP system includes: a base on which an indexing device of a traversing in-core probe used in a nuclear reactor is mounted; a holding part holding the base in a suspended state in an access tunnel formed in a nuclear reactor containment vessel; and a lift mechanism moving up and down the base held by the holding part together with the indexing device.04-28-2011
20110069802CONTROL ROD DRIVE OUTER FILTER REMOVAL TOOL - An outer filter removal tool for a boiling water reactor control rod drive that uses a mechanical advantage obtained through the use of lead screw threads to pull the outer filter off of the control rod drive. Fingers on the tool are closed around the upper flange of the outer filter by sliding a collar over the outwardly biased fingers. A shaft extending through the tool is rotated which in turn extends a push plate against the control rod drive index tube causing the fingers to pull against the upper flange on the outer filter until the filter is freed from the control rod drive. The tool will hold the filter in place until affirmatively released for proper disposal.03-24-2011
20100329408Systems, Apparatuses and Methods of Gripping, Cutting and Removing Objects - A system includes a first platform movably mounted to a first rail assembly, a second rail assembly coupled to and supported by the first platform, and a second platform movably mounted to the second rail assembly. At least one articulating arm is coupled to the second platform, and a gripping and cutting apparatus is coupled to and supported by the at least one articulating arm. An apparatus includes first and second gripping mechanisms each configured for selective actuation between positions for gripping and releasing an object, and a cutting mechanism positioned generally between the first and second gripping mechanisms, and configured to cut the object when gripped on either side by the gripping mechanisms. The system and apparatus can be used to remove feeder pipes of a nuclear reactor power plant.12-30-2010
20110051878Method for Managing Internal Equipment in Reactor Pressure Vessel and Apparatus Thereof - A access apparatus is set on instrumentation nozzles penetrating a bottom portion of a reactor pressure vessel, in the reactor pressure vessel filling water. The access apparatus has an arm turned, and a mounting fixture that can move along the arm and having a holding member. A cover apparatus having a guide pipe covers the access apparatus, and is installed on the bottom portion in underwater environment in the reactor pressure vessel. The water below the cover apparatus is drained from the reactor pressure vessel to form an air space below the cover apparatus. A variety of device heads is suspended and lowered in the air space through the guide pipe, and mounted to the holding member of the mounting fixture. Repair or preventive maintenance operation against the instrumentation nozzles is performed by the variety of device heads.03-03-2011
20100020914REACTOR SERVICING PLATFORM - A servicing platform for a nuclear reactor refueling floor is provided. In various embodiments, the servicing platform includes a base structured to be anchored to a refueling floor of the nuclear reactor. The servicing platform additionally includes a telescoping mast having a mounting collar at a first end that is rotationally attached to the base, and a personnel work basket pivotally coupled to a second end of the mast.01-28-2010
20120148011NUCLEAR REACTOR CAVITY ARRANGEMENTS FOR ICE CONDENSER PLANTS - A pressurized water reactor nuclear containment radiation shield which surrounds the upper portion of a pressure vessel in an ice condenser containment. The vertical walls of the neutron shield are formed in vertical sections with the lower and upper sections operable during outages, to open to promote air flow cooling along the walls in the vicinity of the vessel head.06-14-2012
20120014493REACTOR HEAD SEISMIC SUPPORT TIE ROD SYSTEM - A quick disconnect for a control rod drive mechanism seismic support tie rod system that is remotely operable from a nuclear power plant's operating deck. A wall mounted anchor in the reactor cavity contains one half of a disconnect coupling that interfaces with the other half of the disconnect coupling on the ends of the tie rods employing a remote winching system that is actuated from the top of the reactor head assembly. A latching mechanism is then actuated from the refueling cavity operating deck to lock the tie rod in place and prevent displacement during a seismic or pipe break event. The tie rod may similarly be unlocked from the wall anchor and raised above the reactor head assembly as part of a reactor head disassembly operation to gain access to the core of the reactor vessel for refueling.01-19-2012
20120114090GEROCS Control Rod Blade Unlatching Tool - 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.05-10-2012
20110235768SYSTEMS AND METHODS FOR DISMANTLING A NUCLEAR REACTOR - Systems and methods for dismantling a nuclear reactor are described. In one aspect the system includes a remotely controlled heavy manipulator (“manipulator”) operatively coupled to a support structure, and a control station in a non-contaminated portion of a workspace. The support structure provides the manipulator with top down access into a bioshield of a nuclear reactor. At least one computing device in the control station provides remote control to perform operations including: (a) dismantling, using the manipulator, a graphite moderator, concrete walls, and a ceiling of the bioshield, the manipulator being provided with automated access to all internal portions of the bioshield; (b) loading, using the manipulator, contaminated graphite blocks from the graphite core and other components from the bioshield into one or more waste containers; and (c) dispersing, using the manipulator, dust suppression and contamination fixing spray to contaminated matter.09-29-2011
20080232535Modular nuclear fission reactor - Illustrative embodiments provide modular nuclear fission deflagration wave reactors and methods for their operation. Illustrative embodiments and aspects include, without limitation, modular nuclear fission deflagration wave reactors, modular nuclear fission deflagration wave reactor modules, methods of operating a modular nuclear fission deflagration wave reactor, and the like.09-25-2008
20130170597PREVENTIVE MAINTENANCE/REPAIR DEVICE AND PREVENTIVE MAINENANCE/REPAIR METHOD FOR CYLINDRICAL STRUCTURE - A preventive maintenance/repair device 07-04-2013
20110274232ROBOT SYSTEM FOR LAYING A RAIL TRACK - The invention relates in particular to a robot system comprising a rail track and a robot, which is designed to be displaceable in a direction of movement, guided by the rail track. According to the invention, the rail track consists of a plurality of rail track segments disposed in the direction of movement, and the robot is designed to handle such rail track segments and to extend the rail track by attaching further rail track segments to a respective last rail track segment of the existing rail track. Furthermore, according to the invention, a tension member that is attached to the robot, in particular a tension cable, is provided, which runs along the rail track, wherein a winding device for receiving the tension member is provided in order to introduce a tractive force, preferably in the region of an end of the rail track. The invention is used in particular in order to make it possible to provide a rail track in an area that is difficult or impossible for humans to access and to recover a robot running thereon in the event of damage.11-10-2011
20110274231DUAL DRIVE WINCH AND NUCLEAR REACTOR VESSEL MAINTENANCE APPARATUS EMPLOYING SAME - A dual drive winch having a drive assembly having a first shaft that is selectively movable between a first engaged position and a first disengaged position, and a second shaft that is selectively movable between a second engaged position and a second disengaged position. When the first shaft is in the first engaged position and the second shaft is in the second engaged position simultaneously, rotation of either the first shaft or the second shaft will, through a coupling mechanism, cause rotation of the other of the first shaft and the second shaft.11-10-2011
20130129031APPARATUS FOR VERTICALLY SEGMENTING A BOILING WATER REACTOR CONTROL ROD BLADE - Apparatus for longitudinally segmenting a cruciform shaped irradiated boiling water reactor control rod having four elongated blades radially extending from a central spline, into four flat panels. The apparatus employs a double bladed band saw with the band saw blades orthogonally oriented at two different elevations and having one side of each band saw blade crossing over the center of the spline of the control rod in between the control rod blades.05-23-2013
20100316180JET PUMP RISER BRACE CLAMP - 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.12-16-2010
20100316179CONTROL ROD BLADE EXTENSION FOR A NORDIC NUCLEAR REACTOR - An embodiment of the present invention takes the form of an apparatus or system that may incorporate a single component to connect the control rod blade to the control rod drive system (CRD) of a Nordic-type of BWR. An embodiment of the present invention may eliminate the need of using multiple components to connect the control rod blade with the CRD.12-16-2010
20130195238Method of Repairing Shroud Support and Repair Apparatus Thereof - 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.08-01-2013
20120069947SYSTEM FOR EXCHANGING A COMPONENT OF A NUCLEAR REACTOR - A system for installing or removing a component of a nuclear reactor, such as a CRDM, includes a riser apparatus having a lift assembly structured to hold and support the component and a first drive assembly coupled to the lift assembly and structured to selectively move the lift assembly and the component along a length of the riser apparatus, and a transition cart movable along an under vessel area of the nuclear reactor and having a pivot mechanism, wherein the riser apparatus is selectively engageable with the pivot mechanism and the pivot mechanism is structured to selectively rotate the riser apparatus from a horizontal position to a vertical position. The riser apparatus may also include a second drive assembly structured to selectively move the riser apparatus relative to the transition cart in a direction parallel to a longitudinal axis of the riser apparatus.03-22-2012

Patent applications in class HANDLING OF FISSION REACTOR COMPONENT STRUCTURE WITHIN REACTOR SYSTEM

Patent applications in all subclasses HANDLING OF FISSION REACTOR COMPONENT STRUCTURE WITHIN REACTOR SYSTEM