Class / Patent application number | Description | Number of patent applications / Date published |
376203000 | SEAL ARRANGEMENTS | 25 |
20080279325 | COMPRESSION SLEEVES USABLE IN NUCLEAR REACTORS - A compression sleeve for use in BWR jet pump sensing line repairs is configured to maintain its physical characteristics in an operating nuclear reactor environment. The sleeve includes shaped ends to accommodate deformation and flow of the sleeve so as to form a seal between jet pump sensing line components. A mechanical coupling assembly for repairing a jet pump sensing line is configured to include the compression sleeve. | 11-13-2008 |
20090060110 | Device and method for shutting off an orifice of a bundle wrapper of a steam generator of a pressurized-water nuclear reactor - The invention relates to a device ( | 03-05-2009 |
20100054388 | Sealing Means, Transfer Device Comprising Such a Sealing Means, Arrangement Comprising Such a Transfer Device and a Method for Producing Said Sealing Means - Sealing means comprising a seal carrier and a seal connected thereto, wherein the seal carrier is removably fixable between two areas insulated from each other, and a transfer device between two chambers, which are separated by a wall, wherein said transfer device comprises a transfer mechanism and at least one sealing means according to the invention which is positioned between the wall and the transfer mechanism. | 03-04-2010 |
20110274229 | REACTOR BOTTOM REPAIRING METHOD - A heating laser beam is emitted to a cracked portion to remove moisture from the cracked portion, and subsequently, a welding laser beam is emitted to the cracked portion to heat and melt the cracked portion. The heating laser beam and the welding laser beam are emitted to an entire surface of the cylindrical body inside the reactor such as a stub tube penetrating through and fixed to a reactor bottom portion and a crack of the welded portion between the cylindrical body and the reactor bottom portion to thereby prevent a new crack from occurring and reactor water from leaking. | 11-10-2011 |
20120014492 | INSPECTION HOLE PLUG - [Problem to be Solved] To easily perform assembly at the time of plugging an inspection hole. | 01-19-2012 |
20120027153 | OPENING AND CLOSING DEVICE FOR ACCESS PORT THAT OPENS TO WORKING PLATFORM OF REACTOR VESSEL - An opening and closing device that opens and closes an access port opened from a substantially cylindrical working platform disposed inside a reactor vessel and used to access a nozzle stub of the reactor vessel from the inside of the working platform, the opening and closing device includes: a cover that is slidable along an outer peripheral surface or an inner peripheral surface of the working platform from a closing position where the access port is closed to an opening position where the access port is opened; and moving device for sliding the cover. | 02-02-2012 |
20120106692 | SYSTEMS AND METHOD FOR REDUCING TRITIUM MIGRATION - A system and method for reducing tritium migration. In one aspect, the invention is a method of reducing tritium mitigation from a spent nuclear fuel pool containing a body of tritiated water having an exposed surface, the method comprising hermetically sealing the exposed surface of the body of tritiated water with a cover movable between an open-state and a close-state. | 05-03-2012 |
20130108002 | SHUT-OFF DEVICE FOR A NUCLEAR REACTOR FLUID DUCT, IN PARTICULAR FOR A STEAM GENERATOR BOTTOM DRAIN | 05-02-2013 |
20130170594 | METHODS AND APPARATUSES FOR PUMP SEALING DURING LEAKAGE EVENTS - A pump leakage mitigation device includes one or more clamp arms on an outer surface of a pump that can be driven by a biasing element to seat against a shaft of the pump to seal or reduce fluid flow through a breakdown of the pump. The biasing element engages only at threshold temperatures, such as those associated with breakdown orifice failure when additional sealing may be necessary. Clamp arms of any number and shape can be used to achieve the desired seal and based on the pump geometry. A sealant surface and/or keeping mechanism are useable with the leakage mitigation device to enhance fluid flow blockage throughout a pump failure transient scenario. Pump leakage mitigation devices are installed on an outside of a variety of different pump types and can thus be installed, actuated, manipulated, disengaged, and/or removed without having to destroy or disassemble the pump. | 07-04-2013 |
20130287157 | INSTRUMENTATION AND CONTROL PENETRATION FLANGE FOR PRESSURIZED WATER REACTOR - A nuclear reactor having a penetration seal ring interposed between the reactor vessel flange and a mating flange on the reactor vessel head. Radial ports through the flange provide passage into the interior of the reactor vessel for utility conduits that can be used to convey signal cables, power cables or hydraulic lines to the components within the interior of the pressure vessel. A double o-ring seal is provided on both sides of the penetration flange and partial J-welds on the inside diameter of the flange between the flange and the utility conduits secure the pressure boundary. | 10-31-2013 |
20140169514 | NUCLEAR REACTOR ASSEMBLY HAVING A CONNECTION BETWEEN A CONTROL ROD GUIDE TUBE AND A DRIVE HOUSING PIPE - A boiling water reactor assembly includes a bayonet plate closure between a control rod guide tube and a drive housing pipe. The bayonet plate closure has a bayonet plate constructed in two parts including a central bayonet ring mounted rotatably about its longitudinal axis and an outer ring completely surrounding the bayonet ring. The outer ring is mounted on the periphery of the bayonet ring and reaches inwards under the bayonet ring periphery. The ring is furthermore permanently supported in the axial direction on the drive housing pipe by spring pressure acting on the control rod guide tube, in order to produce a frictional connection. The spring pressure can be released unhindered from the reactor side by tools. | 06-19-2014 |
20140247914 | Narrow Annulus Permanent Canal Seal Plate - An improved permanent seal for a refueling canal of a nuclear power plant is disclosed and claimed. The seal includes a support structure and a membrane. The support structure includes a first annular plate with a number of ribs connected to and extending from a to surface of the support structure annular plate. The support structure is positioned atop the shield wall on the refueling canal floor, encircling and positioned near the annulus. The membrane includes a first end that is connected to the seal ledge and a second end that is connected to the refueling canal floor. The membrane has a stepped profile, with side walls extending substantially perpendicularly from a central annular plate to form a pocket configured to fit over the support structure. Loads imparted to the membrane are transferred through the support structure annular plate and ribs to the refueling canal floor. | 09-04-2014 |
20160042824 | SEALING APPARATUS FOR MITIGATING EMISSIONS OF HAZARDOUS GASES - A sealing apparatus for mitigating emissions of a hazardous gas flowing between first and second regions. A body of the apparatus includes at least one inlet, at least one outlet spaced apart from the at least one inlet, and a channel connecting the at least one inlet and the at least one outlet in fluid communication. Treatment material housed in at least a portion of the channel is adapted to treat the hazardous gas to form a conditioned gas. In use, the hazardous gas being emitted from the first region is received at the at least one inlet, and the conditioned gas is discharged to the second region at the at least one outlet. The apparatus may be used in combination with a storage container housing radioactive or other toxic waste. | 02-11-2016 |
20160118146 | SYSTEMS AND METHOD FOR REDUCING TRITIUM MIGRATION - A system and method for reducing tritium migration. In one aspect, the invention is a method of reducing tritium mitigation from a spent nuclear fuel pool containing a body of tritiated water having an exposed surface, the method comprising hermetically sealing the exposed surface of the body of tritiated water with a cover movable between an open-state and a close-state. | 04-28-2016 |
376204000 | For nozzle | 4 |
20110110476 | Cover Device for Jet Pumps Installed in Nuclear Power Plant Vessels - The invention relates to a plug device for jet pumps installed in nuclear power plant vessels, which comprises two covers ( | 05-12-2011 |
20110194663 | NOZZLE MOUNTING STRUCTURE - [Problem] To facilitate mounting of a nozzle. | 08-11-2011 |
20150325319 | NOZZLE REPAIR METHOD AND NUCLEAR REACTOR VESSEL - A nozzle repair method and a nuclear reactor vessel include: removing a trepanning portion ( | 11-12-2015 |
20150348658 | NOZZLE REPAIR METHOD AND NUCLEAR REACTOR VESSEL - A nozzle repair method and a nuclear reactor vessel include: removing a trepanning portion ( | 12-03-2015 |
376205000 | Between pressure vessel cover and vessel or portion thereof | 7 |
20090028283 | SEALING DEVICE AND METHOD FOR SEALING - A sealing device ( | 01-29-2009 |
20090154631 | HATCH MECHANICAL LOCKING SYSTEM - A locking mechanism for securing hatches internal to a steam generator that is made up of only mechanical locking elements with fully captured moving parts. The mechanism employs a locking pin with redundant mechanisms to secure the pin in the closed position. The moving parts of the device can be attached directly to a removable hatch so that installation and repairs that may be required can be performed outside of the pressure vessel of the steam generator. | 06-18-2009 |
20100310032 | METHOD FOR FILLING THE MAIN PRIMARY COOLANT SYSTEM OF A NUCLEAR POWER PLANT WITH WATER AND FOR DRAINING IT OF AIR, AND HEAD FOR IMPLEMENTING THIS METHOD - The invention relates to a method for the water filling and air blow-off of a main primary circuit ( | 12-09-2010 |
20110116588 | Method for Securing and Confining the Gasket Plane of a Vessel of a Nuclear Reactor and a Gasket for Applying this Method - A method including placing around the shoulder of the lid a ring-shaped gasket formed by a metal strip maintained on the vertical wall of the shoulder by self-maintaining members firmly attached to the strip, placing the lid bearing the ring-shaped gasket above the vessel by positioning it at a determined height, carrying out a cleanliness inspection of the gasket plane, lowering and laying the lid on the vessel so that the end side edges of the strip will come into contact with a horizontal wall of the lid and of the vessel flange respectively and attaching this lid on the vessel. | 05-19-2011 |
20120177164 | REACTOR PRESSURE VESSEL HEAD VENTS AND METHODS OF USING THE SAME - Internal head vents are usable in nuclear reactors and include piping inside of the reactor pressure vessel with a vent in the reactor upper head. Piping extends downward from the upper head and passes outside of the reactor to permit the gas to escape or be forcibly vented outside of the reactor without external piping on the upper head. The piping may include upper and lowers section that removably mate where the upper head joins to the reactor pressure vessel. The removable mating may include a compressible bellows and corresponding funnel. The piping is fabricated of nuclear-reactor-safe materials, including carbon steel, stainless steel, and/or a Ni—Cr—Fe alloy. Methods install an internal head vent in a nuclear reactor by securing piping to an internal surface of an upper head of the nuclear reactor and/or securing piping to an internal surface of a reactor pressure vessel. | 07-12-2012 |
20150085965 | SPACE SAVER FLANGED JOINT FOR A NUCLEAR REACTOR VESSEL - 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. | 03-26-2015 |
20150371724 | INTEGRATED-TYPE PRESSURIZED WATER NUCLEAR REACTOR COMPRISING AN INTEGRATED PRESSURIZER - A pressurized water nuclear reactor includes a primary shell formed by a vessel integrating a core of the nuclear reactor and a cover; a pressurizer built into the shell including hydraulic lines connected to external circuits, the cover of the shell forming an upper wall of the pressurizer, wherein at least one hydraulic line of the pressurizer is formed by: a first line arranged through the vessel of the primary shell and under a plane for positioning the cover onto the vessel, and a second line secured to the cover; the first line and the second line being suitable for sealingly and detachably fitting into one another when the cover is positioned onto the vessel, and a resilient system ensuring the contact between ends of the first and second lines. | 12-24-2015 |