Entries |
Document | Title | Date |
20080232535 | Modular 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 |
20090067564 | System 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 |
20090116606 | JOINT 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 |
20090135985 | MAINTENANCE AND REPAIR DEVICE FOR STRUCTURE INSIDE NUCLEAR REACTOR - A maintenance/repair device for reactor internal structure | 05-28-2009 |
20090245451 | MOBILE 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 |
20090279656 | Apparatuses 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 |
20090285345 | METHOD 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 |
20090323882 | Method 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 |
20090323883 | Method For Carrying Out Reactor Internal - A method for carrying out a reactor internal, comprising steps of:
| 12-31-2009 |
20100002825 | AUTOMATIC 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 |
20100002826 | BOLT 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 |
20100014622 | Nut 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 |
20100020914 | REACTOR 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 |
20100034334 | Pressuriser 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 |
20100046691 | METHOD 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 |
20100150296 | PREVENTIVE MAINTENANCE/REPAIR DEVICE AND PREVENTIVE MAINTENANCE/REPAIR METHOD FOR CYLINDRICAL STRUCTURE - A preventive maintenance/repair device | 06-17-2010 |
20100316179 | CONTROL 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 |
20100316180 | JET 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 |
20100329408 | Systems, 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 |
20110007861 | Machinery 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 |
20110026662 | Instrument 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 |
20110051878 | Method 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 |
20110069802 | CONTROL 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 |
20110096889 | INDEXING 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 |
20110142187 | METHOD 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 |
20110142188 | APPARATUS 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 |
20110235768 | SYSTEMS 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 |
20110235769 | CONTROL 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 |
20110274231 | DUAL 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 |
20110274232 | ROBOT 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 |
20110280359 | SELF 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 |
20110299648 | CONTROL 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 |
20120014493 | REACTOR 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 |
20120069947 | SYSTEM 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 |
20120099692 | SUBMERSIBLE 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 |
20120114090 | GEROCS 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 |
20120148011 | NUCLEAR 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 |
20120224663 | NUCLEAR 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 |
20120236978 | TOOL 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 |
20120294405 | PRESSURIZED 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 |
20130070884 | MAINTENANCE AND REPAIR DEVICE FOR STRUCTURE INSIDE NUCLEAR REACTOR - A maintenance/repair device for reactor internal structure | 03-21-2013 |
20130129031 | APPARATUS 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 |
20130170597 | PREVENTIVE MAINTENANCE/REPAIR DEVICE AND PREVENTIVE MAINENANCE/REPAIR METHOD FOR CYLINDRICAL STRUCTURE - A preventive maintenance/repair device | 07-04-2013 |
20130195238 | Method 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 |
20130287160 | RISER TRANSITION ELEMENT FOR COMPACT NUCLEAR REACTOR - A nuclear reactor core is disposed in a pressure vessel along with upper internals disposed in the pressure vessel above the reactor core. The upper internals include internal control rod drive mechanisms (CRDMs) mounted on a suspended support assembly. A hollow cylindrical central riser is disposed in the pressure vessel above the nuclear reactor core. A hollow cylindrical section is disposed in the pressure vessel below the hollow cylindrical central riser and surrounding the nuclear reactor core. A riser transition element connects with the hollow cylindrical central riser and the hollow cylindrical section to form a continuous hollow cylindrical flow separator. The suspended support assembly of the upper internals is suspended from the riser transition element. The pressure vessel may comprise upper and lower vessel sections connected by a mid-flange, with the riser transition element welded to the mid-flange by gussets extending outward and upward from the riser transition element to the mid-flange. | 10-31-2013 |
20140098924 | APPARATUS AND METHOD TO CONTROL SENSOR POSITION IN LIMITED ACCESS AREAS WITHIN A NUCLEAR REACTOR - 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. | 04-10-2014 |
20140126681 | SUPPORT PIN REPLACING APPARATUS FOR CONTROL ROD CLUSTER GUIDE TUBE - The support pin replacing apparatus for a control rod cluster guide tube includes a frame submerged in water, a movement device that holds the control rod cluster guide tube and moves the control rod cluster guide tube along the frame, a retrieval manipulator that retrieves a support pin of the control rod cluster guide tube under the water, a supply manipulator that supplies a new support pin to the control rod cluster guide tube under the water, a rotating means that imparts rotation for loosening or tightening a fastening between a nut of the support pin or the new support pin and the support pin main body, and a control device that calculates variation in distance between the nut and the support pin main body on the basis of the rotation, and controls the control rod cluster guide tube to move along the frame. | 05-08-2014 |
20140185728 | SYSTEMS AND METHODS FOR DISPOSING OF ONE OR MORE RADIOACTIVE COMPONENTS FROM NUCLEAR REACTORS OF NUCLEAR PLANTS - 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. | 07-03-2014 |
20140314195 | LIFTING SHACKLE OF HEAD ASSEMBLY FOR NUCLEAR REACTOR - 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 first connection member. | 10-23-2014 |
20140328444 | NUCLEAR FISSION REACTOR, A VENTED NUCLEAR FISSION FUEL MODULE, METHODS THEREFOR, AND A VENTED NUCLEAR FISSION FUEL MODULE SYSTEM - Illustrative embodiments provide a nuclear fission reactor, a vented nuclear fission fuel module, methods therefor and a vented nuclear fission fuel module system. | 11-06-2014 |
20140362967 | Reactor Measurement-Pipe Maintenance Clamp Apparatus - 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. | 12-11-2014 |
20150016582 | COOLING DUCT ASSEMBLY FOR CONTROL ELEMENT DRIVE MECHANISM - 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. | 01-15-2015 |
20150071397 | Remotely Installed Fuel Transfer Tube Closure System - 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. | 03-12-2015 |
20150332796 | MANAGEMENT EQUIPMENT TRANSFER APPARATUS - A management equipment transfer apparatus which transfers management equipment, which tests and maintains an inside of a nuclear reactor vessel, inside the nuclear reactor vessel while being locked to the management equipment and the nuclear reactor vessel, includes: a cross beam configured to be lengthily disposed inside the nuclear reactor vessel in a transverse direction; a rod configured to be connected to a cross beam lengthily disposed inside the nuclear reactor vessel in a longitudinal direction; a bracket configured to be mounted in the rod to fix the management equipment; an arm configured to extend toward an inner peripheral surface of the nuclear reactor vessel and be connected to the cross beam; and rolling parts configured to be disposed at ends of the arm and the cross beam, contact the inner peripheral surface of the nuclear reactor vessel, and rotatably support the cross beam and the arm. | 11-19-2015 |
20150348657 | ANCHOR DEVICE AND NUCLEAR FACILITY COMPRISING SUCH AN ANCHOR DEVICE - An anchor device and a nuclear facility comprising such an anchor device are provided. This anchor device comprises a female part and a male part, the female part comprising a groove extending along a longitudinal axis, the groove having a width which decreases longitudinally and a transverse section, the male part comprising a slider with a shape mating that of the groove and able to be longitudinally inserted into the groove, the transverse section of the groove being configured so as to prevent the extraction of the slider out of the groove transversely to the longitudinal axis. The anchor device comprises a locking device able to prevent the slider from longitudinally sliding out of the groove. | 12-03-2015 |
20160035443 | TREATMENT APPARATUS FOR WASTE STEAM GENERATOR AND INSTALLATION METHOD THEREOF - A treatment apparatus includes a cutting part for cutting a lower head of a waste steam generator, a driving part for driving the cutting part, and a support frame for supporting the cutting part and the driving part, wherein the support frame is coupled to an outer peripheral surface of the lower head in a divided state, and the cutting part is driven and cuts the lower head in a state in which the support frame is coupled to the outer peripheral surface of the lower head. Since the support frame is divided into a plurality of portions and a dedicated installation jig is provided, the treatment apparatus is easily moved and installed and installation time thereof can be shortened, and an exposure time of a worker can be minimized. | 02-04-2016 |
20160042820 | CHIMNEY ASSEMBLY OF A REACTOR PRESSURE VESSEL AND METHOD OF STORING THE SAME DURING A NUCLEAR REACTOR OUTAGE - A method of storing a chimney assembly of a reactor pressure vessel during a nuclear reactor outage may include detaching a chimney barrel with upper chimney partitions therein from a top guide assembly of the reactor pressure vessel. A height of the upper chimney partitions is less than a height of the chimney barrel so as to leave a plenum region in a top section of the chimney barrel. The top guide assembly includes lower chimney partitions therein. The lower chimney partitions are removed from the top guide assembly and inserted into the plenum region of the chimney barrel so as to be on the upper chimney partitions. As a result, the chimney assembly can be stored in a relatively compact form during a reactor outage. The chimney assembly may be a combination of at least the chimney barrel, the upper chimney partitions, and the lower chimney partitions. | 02-11-2016 |
20160141057 | Excavation and Weld Repair Methodology for Pressurized Water Reactor Piping and Vessel Nozzles - The invention is an innovative design/repair methodology for PWR piping nozzles and vessel nozzles that are attached to the piping/vessel base material with a full penetration weld joint geometry. The development of a robust repair methodology for nozzles of this configuration is necessary due to plant aging, potential material degradation in the original materials of construction, potential increased nondestructive examination requirements, and PWSCC phenomena in the susceptible original materials of construction. The purpose/objective of the repair methodology is to provide a means of partially replacing the existing pressure boundary susceptible materials with PWSCC-resistant materials to facilitate the long-term repair life of the plant. The invention may be applied to a plurality of nozzle, piping, and vessel sizes with a full penetration weld joint. | 05-19-2016 |
20190148026 | FLANGE FLUSH TOOL | 05-16-2019 |
20220139580 | ANTI-ROTATION ARRANGEMENT FOR THERMAL SLEEVES - Arrangements and devices for reducing and/or preventing wear of a thermal sleeve in a nuclear reactor are disclosed. Arrangements include a first structure provided on or in one the thermal sleeve and a second structure provided on or in the head penetration adapter. At least a portion of the first structure and at least another portion of the second structure interact to resist, reduce, and/or prevent rotation of the thermal sleeve about its central axis relative to the head penetration adapter. Devices include a base for coupling to a guide tube of the reactor and a plurality of protruding members extending upward from the base. Each member having a portion for engaging a corresponding portion of a guide funnel of the thermal sleeve. | 05-05-2022 |
20220139583 | METHOD FOR DISMANTLING NUCLEAR FACILITY UNDERWATER - An underwater decommissioning method of a nuclear facility is disclosed. An underwater decommissioning method of a nuclear facility that includes a nuclear reactor pressure vessel and bio-protective concrete including a cavity in which the nuclear reactor pressure vessel is positioned, includes: (a) floating the nuclear reactor pressure vessel above the cavity; (b) forming an insertion part filled with water in a side spaced apart from the cavity, and installing a support part on a bottom surface of the insertion part; (c) mounting a lower portion of the nuclear reactor pressure vessel on the support part; and (d) repeatedly cutting and decommissioning the nuclear reactor pressure vessel mounted on the support part by using a cutting device in an underwater position. | 05-05-2022 |