| Class / Patent application number | Description | Number of patent applications / Date published |
|---|
| 376249000 | Vessel monitoring or inspection | 40 |
| 20080205575 | Method of inspecting or utilizing tools in a nuclear reactor environment - A method of inspecting or utilizing tools in the underwater environment of a nuclear reactor vessel, a spent fuel pool or equipment pit includes floating a platform for transporting inspection devices and/or tools over an underwater target site and deploying the devices or tools to the underwater target site. The platform may be coupled to a boom whose opposite end is carried by a cart movable about a floor area surrounding the pool. Alternatively, the platform may be independently movable along the water surface by thrusters. | 08-28-2008 |
| 20080240331 | INSPECTION APPARATUS FOR REACTOR BOTTOM MOUNTED INSTRUMENTATION NOZZLE - Provided is an inspection apparatus for a reactor BMI nozzle. The apparatus includes a motor, a ball screw, a guide, and a coil spring. The motor is installed at a transmission of a bracket provided under a quick connector of an ROSA-V six-axis system and enables vertical driving of an inspection probe. The ball screw converts a rotary motion of the motor into a vertical motion and vertically reciprocating the inspection probe. The guide compels an axial arrangement of the inspection probe and removes eccentricity generated when the inspection probe is inserted into the nozzle. The coil spring is installed above the guide and prevents an impact propagation of an instrument. | 10-02-2008 |
| 20080317192 | Inspection, maintenance, and repair apparatuses and methods for nuclear reactors - An apparatus for inspecting a nuclear reactor may include a track, arm, fixing device, and effector. The arm may be operatively connected to the track, the fixing device may be operatively connected to the track, and the effector may be operatively connected to the arm. The arm may have contracted and expanded lengths. The expanded length may be greater than two times the contracted length. The track may include one or more motors adapted to move the arm relative to the track. A method of inspecting, performing maintenance on, or repairing a reactor may include: operatively connecting a fixing device, track, arm, and effector to form an apparatus; inserting the apparatus into the reactor; fixing the apparatus within the reactor; and operating the apparatus. A method of operating a reactor may include shutting down; inspecting, performing maintenance on, or repairing the reactor; and starting up the reactor. | 12-25-2008 |
| 20090122942 | APPARATUS FOR ULTRASONIC INSPECTION OF REACTOR PRESSURE VESSEL - An object of the present invention is to provide an inspection apparatus for inspecting weld zones in a reactor pressure vessel, the inspection apparatus comprising: an ultrasonic probe | 05-14-2009 |
| 20090129527 | Refueling apparatus for sodium-cooled fast reactor and method for the same - A refueling apparatus for charging nuclear fuel in a reactor vessel, the refueling apparatus including: a refueling unit loading new nuclear fuel to a core or extracting spent nuclear fuel from the core; and a waveguide sensor unit including an ultrasonic wedge to form a Lamb wave, a waveguide with an end connected to the ultrasonic wedge and with another end transmitting the Lamb wave into the reactor vessel, and an ultrasonic sensor connected to the ultrasonic wedge and sensing a reflection signal reflected from an inside of the reactor vessel, the waveguide being formed in a plate shape and mounted in an end of the refueling unit. The waveguide integrally moves with the refueling unit, and the waveguide sensor unit detects a condition of the inside of the reactor vessel, while the refueling unit refuels the fuel assembly in the reactor vessel. | 05-21-2009 |
| 20100119028 | Nuclear reactor steam dryer manipulator - A BWR steam dryer remote visual inspection system including a support moveable along a first axis over the steam dryer, the support having a longitudinal direction; a trolley movable along the support in the longitudinal direction; a mast fixed to the trolley and moveable at a predetermined angle with respect to a plane defined by the first axis and longitudinal direction; and a camera coupled to an end of the mast. | 05-13-2010 |
| 20100232562 | WORKING DEVICE AND WORKING METHOD - A working apparatus has: a working equipment for doing works on a structure; a folding/unfolding mechanism for conveying the working equipment to the working position in a folded state; a conveyance mechanism (such as a horizontal thruster) for conveying the working equipment and the folding/unfolding mechanism to the working position; a pressing mechanism (such as a ballast tank) for pressing the working equipment against the lower surface of the structure; and a traveling mechanism including a wheel for traveling along the lower surface of the structure and positioning the apparatus. | 09-16-2010 |
| 20110091002 | UNDERWATER REMOTE INSPECTION DEVICE AND METHOD FOR UNDERWATER REMOTE INSPECTION - An underwater remote inspection device is provided with an etching device and a magnifying observation device mounted to a supporting member. A chamber of the etching device is provided with a negative electrode, a positive electrode and a sealing device, and is connected to an etchant supply pipe and an etchant exhaust pipe. A single pair of annular sealing members of the sealing device is provided to a distal end portion of the chamber. A suction passage formed in the side wall of the chamber communicates to a sealing region formed between the sealing members. The magnifying observation device is provided with a magnifying camera in a waterproof container and a plurality of LED lights are installed to the waterproof container. The underwater remote inspection apparatus can prevent leakage of an etchant and reduce execution time of etching. | 04-21-2011 |
| 20110096888 | APPARATUS FOR ULTRASONIC INSPECTION OF REACTOR PRESSURE VESSEL - An object of the present invention is to provide an inspection apparatus for inspecting weld zones in a reactor pressure vessel, the inspection apparatus comprising: an ultrasonic probe | 04-28-2011 |
| 20110103536 | APPARATUS FOR ULTRASONIC INSPECTION OF REACTOR PRESSURE VESSEL - An object of the present invention is to provide an inspection apparatus for inspecting weld zones in a reactor pressure vessel, the inspection apparatus comprising: an ultrasonic probe | 05-05-2011 |
| 20110142186 | METHOD AND DEVICE FOR DETECTING DEPOSITS COMPRISING AT LEAST ONE FERROMAGNETIC MATERIAL ON OR NEAR THE EXTERNAL WALL OF A TUBE - The present invention relates to a method of detecting deposits comprising at least one ferromagnetic material, such as nickel, magnetite or the like, on or near the external wall of a tube, notable in that it comprises at least the following steps of: moving a magnetized source inside the tube in the lengthwise direction using an electric motor, measuring the strength of the current in the electric motor, and determining the position and/or the thickness and/or the volume of the said deposit as a function of the variations in the strength of the current measured in the electric motor. Another subject of the invention is a device implementing the said method. | 06-16-2011 |
| 20110158371 | PRESSURIZED WATER REACTOR PLANT - According to an embodiment, a pressurized water reactor plant has a primary system which includes: a reactor vessel for housing a reactor core which is cooled by a primary coolant, a single steam generator, a hot leg pipe for connecting the reactor vessel and the steam generator, cold leg pipes, at least two primary coolant pumps, and a pressurizer for pressurizing the primary coolant pressure boundary in which the primary coolant flows. The plant also has: a passive cooling and depressurization system which is a primary depressurization means for equalizing the primary system pressure to the secondary system pressure at the time of a tube rupture accident of the steam generator, and a reactor containment vessel containing the primary system and cooling the primary system by air cooling. Thus, a compact pressurized water rector with high economic efficiency, safety, and reliability can be provided. | 06-30-2011 |
| 20110235767 | INSPECTION TOOL FOR TOP GUIDES OF A BOILING WATER REACTOR - A tool for inspecting a cell formed by grid beams of a top guide structure in a nuclear reactor is provided. The tool includes a camera; a support structure coupled to the camera for contacting at least one of the grid beams to support the camera within the cell; and at least one actuator moving the camera with respect to the support structure and along one of the grid beams, the at least one actuator coupling the camera to the support structure. A method for inspecting a cell formed by grid beams of a top guide structure in a nuclear reactor is also provided. | 09-29-2011 |
| 20110268238 | APPARATUS AND METHOD FOR AUTOMATICALLY AND REMOTELY MEASURING THE INTERNAL GAP OF A REACTOR - A remote, precise gap-measuring apparatus for automatically measuring the gap between reactor internals, including a nuclear reactor vessel, a core support barrel, a core shroud, and a lower support structure. The remote, precise gap-measuring apparatus includes digital probes measuring a gap between a nuclear reactor vessel protrusion and a core support barrel protrusion. The nuclear reactor vessel protrusions are disposed on an inner surface of the nuclear reactor vessel, and the core support barrel protrusions are disposed on an outer surface of the core support barrel, engaged with the nuclear reactor vessel protrusions. The apparatus includes a computer coupled to the digital probes to display and store measured values of the gap. A solenoid valve, controlled by the computer, controls compressed air supplied through an air hose to operate the digital probe. The digital probes are used to measure the gap after the core support barrel, the core shroud, and the lower support structure are welded to each other, decreasing construction time and simplifying construction. | 11-03-2011 |
| 20110317796 | VIBRATION MEASURING APPARATUS FOR NUCLEAR REACTOR INTERNAL STRUCTURE AND VIBRATION MEASUREMENT METHOD THEREFOR - A vibration measuring apparatus for nuclear reactor internal structure includes a holder which has an opening contact on a surface of a pressure vessel of a nuclear reactor; a vibrator accommodated in the holder so as to transmit or receive an ultrasonic wave; a couplant with which the holder is filled up; and, a bias component applies a biasing force to the vibrator in the direction of the opening; The couplant is a solid state of metal material at normal temperature and change to liquid stage by heat transfer from the pressure vessel. | 12-29-2011 |
| 20120002775 | ASSEMBLY AND METHOD FOR DETECTING AND MEASURING THE FOULING RATEOF FLOW HOLES IN A SECONDARY CIRCUIT OF A PRESSURIZED WATER NUCLEAR REACTOR - An assembly for detecting and measuring the fouling rate by deposits containing at least one ferromagnetic material, including a probe which can be continuously moved inside a tube and which has a body carrying on its outer surface at least one magnetized source for self-orientation of the body of the, at least three magnetic field emitters and at least three magnetic field detectors each positioned between two contiguous emitters. | 01-05-2012 |
| 20120027154 | NOZZLE STUB WORKING SYSTEM FOR REACTOR VESSEL - Disclosed is a nozzle stub working system for a reactor vessel that performs work inside a nozzle stub of the reactor vessel, the nozzle stub working system for the reactor vessel including: a platform unit that is provided at an upper portion inside the reactor vessel and includes a substantially cylindrical side wall portion and a bottom portion blocking the lower end of the side wall portion; an access window that is provided at the side wall portion of the platform unit to allow the inside of the platform unit to communicate with the nozzle stub; an access window moving device that opens and closes the access window; a working device that advances from the inside of the platform unit to the inside of the nozzle stub to perform work inside the nozzle stub; and a control device that is provided at the outside of the reactor vessel and controls the access window moving device and the working device, wherein the control device drives the access window moving device to open the access window, drives the working device to perform work inside the nozzle stub, and then drives the access window moving device to close the access window after the performance of the work. | 02-02-2012 |
| 20120140865 | Core Shroud Weld Inspection Systems and Methods - An inspection system for inspecting a core shroud includes a remotely operated vehicle with a profile, scanning ability, and reliability that contribute to expanded inspection coverage and reduced inspection times. | 06-07-2012 |
| 20120148010 | TOP GUIDE INSPECTION FIXTURE - A fixture for performing visual inspections of the underside of the top guide of a boiling water reactor. The inspections are performed in the reactor vessel, under water, and includes a framed structure that rests on top of the top guide and supports a wheel track within a fuel assembly opening in the top guide, that follows the contour of the opening. A camera support, suspended from the frame, is then remotely, manually rotated to follow the contour of the wheel track as the fixture maintains the camera at a fixed angle and known constant distance from the underside of the top guide. | 06-14-2012 |
| 20120177165 | CONSTRUCTION METHOD, TUBULAR MEMBER, AND NUCLEAR POWER PLANT - A construction method of a pipeline that forms a pipeline by joining tubular members to each other by butt welding, includes: a tubular member preparation step for preparing a tubular member having a smooth length of an outer surface along an axial direction from a joined end, which is set based on conditions of ultrasonic inspection of a welded portion, which are determined by usage conditions of the pipeline; a tubular member welding step for welding together prepared tubular members; and a welded portion inspection step for inspecting a welded portion by ultrasonic inspection. | 07-12-2012 |
| 20120243649 | IN-REACTOR WORK SYSTEM AND IN-REACTOR WORK METHOD - According to an embodiment, an in-reactor operation system which is provided with a crack detection vehicle that moves in a circumferential direction along an outer surface of a shroud disposed in a reactor pressure vessel with the axis vertical, an inspection/check sensor that is mounted on the crack detection vehicle and performs an operation with respect to the shroud, a vehicle positioning mast for setting an initial position of the crack detection vehicle on the shroud, a vehicle fixation mechanism for attaching and detaching the crack detection vehicle to and from the vehicle positioning mast, and a conveyance vehicle for conveying the vehicle positioning mast on which the crack detection vehicle is mounted into the reactor pressure vessel. | 09-27-2012 |
| 20120257704 | APPARATUS AND METHOD OF WIRELESS UNDERWATER INSPECTION ROBOT FOR NUCLEAR POWER PLANTS - An inspection robot for inspecting a nuclear reactor that includes a hull and an on-board control mechanism that controls the operation of the inspection robot. The on-board control mechanism controls one or more sensors used to inspect one or more structures in the nuclear reactor as well as the movement by the inspection robot. A gimbal mechanism rotates the inspection robot hull by shifting the center-of-mass so that gravity and buoyancy forces generate a moment to rotate the hull in a desired direction. A camera is coupled to the gimbal mechanism for providing visual display of the one or more structures in the nuclear reactor. The camera is allowed to rotate about an axis using the gimbal mechanism. The inspection robot communicates its findings with respect to the inspection tasks using the wireless communication link. | 10-11-2012 |
| 20120257705 | METHOD OF DETECTING AN EXISTENCE OF A LOOSE PART IN A STEAM GENERATOR OF A NUCLEAR POWER PLANT - A plurality of signal anomalies are identified in a number of tubes in a steam generator. Since the geometry of the steam generator is known, the location of each signal anomaly along each tube is converted into a location within the interior of the steam generator. If a plurality of signal anomalies are at locations within the steam generator that are within a predetermined proximity of one another, such a spatial confluence of signal anomalies is determined to correspond with a loose part situated within the steam generator. Additional methodologies can be employed to confirm the existence of the loose part. Historic tube sheet transition signal data can be retrieved and subtracted from present signals in order to enable the system to ignore the relatively strong eddy current sensor signal of a tube sheet which would mask the relatively weak signal from a loose part at the tube sheet transition. | 10-11-2012 |
| 20130044849 | WATER-CHAMBER WORKING APPARATUS - A water-chamber working apparatus ( | 02-21-2013 |
| 20130121451 | Nuclear Reactor Vibration Monitoring Apparatus and Method of Monitoring Nuclear Reactor Vibration - Vibration of a jet pump installed in a reactor pressure vessel of a boiling water reactor is monitored. Ultrasonic waves are transmitted from an ultrasonic sensor installed on an outer surface of the reactor pressure vessel toward a throat and a diffuser of the jet pump. When the ultrasonic waves reach respective outer surfaces of the throat and diffuser, reflected waves are generated at the respective outer surfaces. The ultrasonic sensor receives those reflected waves. The ultrasonic signal process section obtains a distance in the horizontal direction between the throat and the diffuser based on a time difference of the reflected waves reflected from respective reflection surfaces of the throat and diffuser and a sound speed in reactor water in the neighborhood of the throat and diffuser. A relative vibration is obtained based on the change with time of the distance. | 05-16-2013 |
| 20130195236 | Preventive Maintenance Method and Apparatus for a Structural Components in a Reactor Pressure Vessel - Disclosed is a water jet peening method that includes the steps of: preparing a water jet peening apparatus having a supporting member, a first divider plate, a nozzle support body, and a second divider plate; inserting the water jet peening apparatus into a piping in which a structure or electronic device is mounted that is susceptible to damage by a jet of water discharged from a jet nozzle or by shock waves; disposing either the first divider plate or the second divider plate between the jet nozzle and the structure or electronic device; filling water into an internal area formed in the piping between the first divider plate and the second divider plate; and subjecting the inner surface of the piping to water jet peening by allowing the jet nozzle to discharge a jet of water into the water in the internal area. | 08-01-2013 |
| 20130243144 | METHOD AND APPARATUS OF INSPECTING THE UPPER CORE SHROUD OF A NUCLEAR REACTOR VESSEL - A method and apparatus for inspecting the upper portion of a core shroud of a nuclear power plant is provided. The upper shroud scanner mounts on an arcuic section of a steam dam of the core shroud and moves back and forth there along. A vertical arm with transducers thereon extend down from a Y-car portion of the upper shroud scanner. Transducers adjacent the core shroud emit and receive an ultrasonic sound to inspect for flaws and defects in the core shroud. | 09-19-2013 |
| 20130243145 | Nozzle Inspection Tool for Nuclear Power Plants - A device is provided to inspect welds in nozzles located in water within a containment vessel of a nuclear power plant. A computer connected to the device controls movement by use of thrusters located along a main rail while buoyancy packs regulate the depth. After the device is navigated to a weld needing inspection, feet extend radially outward from the main rail to secure the device in the nozzle. Then transducer clusters are moved along the main rail to be radially inside the weld to be inspected. Thereafter, the transducer clusters are extended radially outward and rotated adjacent to the weld while simultaneously emitting test signals and receiving reflected signals to indicate the condition of the weld. | 09-19-2013 |
| 20130266109 | AUTOMATED INSIDE REACTOR INSPECTION SYSTEM - An apparatus and method for maintaining contact between a pod of transducers and an inner surface of a reactor pressure vessel filled with water of a nuclear power plant is described. An underwater carriage carries the pod of transducers each of which is independently movable and are constantly urged against the surface of the vessel during inspection. Each transducer is independently pivotable about two axes. Each transducer emits and receives signals to detect any flaws of potential problems in the reactor pressure vessel. | 10-10-2013 |
| 20130272469 | DEVICE AND METHOD FOR REACTOR AND CONTAINMENT MONITORING - A device for monitoring a reactor during normal and off-normal operating conditions may include a case formed of a rigid material, the case including a shielding layer configured to insulate an internal portion of the device from external heat and radiation; a coupling unit configured to adhere the case to a surface location of a reactor; a sensing unit configured to generate environmental measurements by measuring environmental conditions in the vicinity of the reactor; a data processing unit configured to generate measurement data by processing the environmental measurements; a transmitter configured to transmit the measurement data externally from the device; and a power unit configured to power the device independently of an external power source. | 10-17-2013 |
| 20130329848 | CAMERA INSPECTION ARM FOR BOILING WATER REACTOR - There is disclosed a remotely deployed and operated boiling water reactor camera inspection arm. In an embodiment, the remotely deployed and operated boiling water reactor camera inspection arm has a vertical actuator, that includes a bi-stable lightweight reelable tube configurable from a rolled retracted state to an extended tubular state by unrolling downwardly, and back to a rolled retracted state by rolling upwardly. An inspection camera is attached to an end of the reelable tube. Other embodiments are also disclosed. | 12-12-2013 |
| 20140064424 | Method of separating amorphous iron oxides - A method for separating amorphous iron oxides is provided. The method includes steps of sampling, filtering, dissolving and separating, analyzing the solution containing amorphous radioactive iron oxides and analyzing granules containing crystalline radioactive iron oxides. Characteristics of the radioactive iron oxides during various periods are acquired to solve the radiation buildup problem. Parameters for improving water quality and chemistry performance indicator are thus provided. Crystalline deposits are separated while the dissolving rate of radioactive iron oxides reaches more than 90%. The present invention does not use complex utilities, is easy to use and has a low operation cost for fast analysis. | 03-06-2014 |
| 20140098922 | APPARATUS AND METHOD TO INSPECT, MODIFY, OR REPAIR NUCLEAR REACTOR CORE SHROUDS - This invention generally concerns robotic systems and is particularly concerned with improved apparatus and methods for remotely inspecting, modifying or repairing a core shroud in a nuclear reactor. The apparatus of the invention includes a partial upper track which horizontally movable along the core shroud, a head and frame assembly which is horizontally movable along the partial upper track, a lower track which is connected to the head and frame assembly and is horizontally movable along the core shroud, and a carriage and arm assembly which extends downward into an annulus formed by the reactor pressure vessel and the core shroud, wherein the arm includes at least one sensor for inspecting the core shroud. | 04-10-2014 |
| 20140211902 | INSPECTION APPARATUS FOR PENETRATION PIPE OF NUCLEAR REACTOR HEAD - An inspection apparatus for a penetration pipe of a nuclear reactor head comprising: a body; a probe module installed at the body and having a probe which is inserted in the penetration pipe to inspect damage of the penetration pipe; a fixing module installed along a longitudinal direction of the body and having an expanding cylinder which is inserted in the penetration pipe to support an inner diameter of the penetration pipe; and a rotating module installed in the longitudinal direction of the body and having an expanding cylinder which is inserted in the penetration pipe to support the inner diameter of the penetration pipe. | 07-31-2014 |
| 20140241482 | INSPECTION METHOD AND INSPECTION DEVICE - There is provided an inspection device for inspecting an inner surface of a nozzle provided in a reactor vessel. The inspection device includes: a device frame, an inspection unit provided on the device frame, an inspection unit push-out moving mechanism for pushing out and moving the inspection unit to the inner surface of the nozzle, a rotation moving mechanism for rotating and moving the inspection unit, a calibration test unit arranged on the device frame for calibrating the inspection unit; and a calibration test unit forward/backward moving mechanism for moving the calibration test unit forward or backward in the direction along the central axis with regard to a track where the inspection unit makes push-out movement. | 08-28-2014 |
| 20140270038 | APPARATUS AND METHOD TO INSPECT NUCLEAR REACTOR COMPONENTS IN THE CORE ANNULUS, CORE SPRAY AND FEEDWATER SPARGER REGIONS IN A NUCLEAR REACTOR - This invention generally concerns robotic systems and is specifically concerned with an improved apparatus and method for inspecting nuclear reactor components in limited access areas, such as, the core annulus, core spray and feedwater sparger regions of a nuclear reactor. This invention includes an apparatus for remotely operating and positioning at least one inspection device for inspecting at least one component in an annulus region of a reactor pressure vessel of a nuclear power plant. The apparatus includes a track, a braking system and a frame assembly which has a frame movably connected to the track, at least one mast assembly and at least one mast positioning assembly. The at least one inspection device is attached to the at least one mast assembly. In certain embodiments, the at least one mast assembly includes a mast that is capable of becoming rigidly stable in both an extended tube form and a retracted rolled form. | 09-18-2014 |
| 20140341329 | DEVICE FOR MONITORING AND COLLECTING INFORMATION FROM AN AREA WITH POTENTIAL RISK OF IRRADIATION - A device for monitoring and collecting information ( | 11-20-2014 |
| 20140355729 | NUCLEAR PLANT MANIPULATOR SYSTEM - A nuclear plant manipulator system is disclosed which can include a manipulator with an image acquisition device and remote-control drive, a remote-operating device, as well as an analysis device for analyzing image data of the image acquisition device. The analysis device can be configured in such a way that when the manipulator moves along a path of movement based on image data, respective known objects that are found along the path of movement are automatically identified, and when such an object is passed, depending on the direction, an object counter is incremented or decremented, whereby the current value of the object counter is provided to the remote-operating device. A method is disclosed for controlling a manipulator of the nuclear plant manipulator system. | 12-04-2014 |
| 20150131767 | CONSTRUCTION METHOD, TUBULAR MEMBER, AND NUCLEAR POWER PLANT - A construction method of a pipeline that forms a pipeline by joining tubular members to each other by butt welding, includes: a tubular member preparation step for preparing a tubular member having a smooth length of an outer surface along an axial direction from a joined end, which is set based on conditions of ultrasonic inspection of a welded portion, which are determined by usage conditions of the pipeline; a tubular member welding step for welding together prepared tubular members; and a welded portion inspection step for inspecting a welded portion by ultrasonic inspection. | 05-14-2015 |
| 20150332794 | TRANSPORTABLE MONITORING SYSTEM - A system for monitoring a reactor module housed in a reactor bay may include a mounting structure and one or more extendable attachment mechanisms connected to the mounting structure. Additionally, one or more monitoring devices may be operably coupled to the one or more extendable attachment mechanism, and the one or more extendable attachment mechanisms may be configured to selectively position the one or more monitoring devices at varying distances from a wall of the reactor bay to place the one or monitoring devices in proximity to the reactor module. | 11-19-2015 |
