HITACHI-GE NUCLEAR ENERGY, LTD. Patent applications |
Patent application number | Title | Published |
20150228362 | CORE OF LIGHT WATER REACTOR AND FUEL ASSEMBLY - A core of a light water reactor has a plurality of fuel assemblies. The fuel assemblies include a plurality of fuel rods in which a lower end is supported by a lower tie-plate and an upper end is supported by an upper tie-plate. The fuel rods form plenums above a nuclear fuel material zone and have a neutron absorbing material filling zone under the nuclear fuel material zone. Neutron absorbing members attached to the upper tie-plate are disposed between mutual plenums of the neighboring fuel rods above the nuclear fuel material zone. The neutron absorbing members have a length of 500 mm and are positioned at a distance of 300 mm from the nuclear fuel material zone. Even if the overall core is assumed to become a state of 100% void, no positive reactivity is inserted to the core. | 08-13-2015 |
20140367075 | PLATE HEAT EXCHANGER - To provide a plate heat exchanger free from degradation of gaskets which form a flow path through which a high-temperature fluid flows. In the plate heat exchanger, a plurality of heat transfer plates | 12-18-2014 |
20140355378 | Ultrasonic Observation Equipment, Ultrasonic Observation System, and Ultrasonic Observation Method - A single-element ultrasonic sensor includes a single transducer element and transmits an ultrasonic wave on the basis of a pulse wave. An ultrasonic array sensor includes a plurality of transducer elements and receives an ultrasonic reflected wave. A pulsar supplies the pulse wave to the single element ultrasonic sensor. A receiver receives electric signals from the transducer elements included in the ultrasonic array sensor. An amplification and conversion unit amplifies the electric signals received from the transducer elements included in the ultrasonic array sensor, converts the electric signals into digital signals, and arranges the digital signals in a serial order so as to generate a serial digital signal. An image generator generates an image on the basis of the serial digital signal. | 12-04-2014 |
20140338870 | PLATE HEAT EXCHANGER - Heat transfer plates are stacked, each being provided with a plurality of passage holes, a flow-path forming gasket is interposed between peripheries of each adjacent ones of the heat transfer plates, thereby alternately forming a first flow path to pass a high-temperature fluid, a second fluid to pass a low-temperature fluid, and communicating paths to cause the fluids to flow in and out of the first flow path and the second flow path on opposite sides of each heat transfer plate, and communicating-path forming gaskets surrounding the passage holes are interposed between adjacent ones of the heat transfer plates, thereby forming a communicating path to cause a fluid to flow in and out of the first flow path and a communicating path to cause a fluid to flow in and out the second flow path. Each communicating-path forming gasket is made up of inner and outer gasket members arranged in two lines, the inner gasket member surrounding the passage holes while the outer gasket member surrounding the inner gasket member. | 11-20-2014 |
20140331771 | Ultrasonic Measurement System - Disclosed is an ultrasonic measurement system that even without additional means for temperature measurement, compensates for a change in a sound speed of an ultrasonic wave in a section whose thickness is to be measured, and assesses a wall thinning state of this section by highly accurate measurement of the thickness. | 11-13-2014 |
20140254738 | ALTERNATIVE AIR SUPPLY AND EXHAUST PORT FOR AIR-OPERATED VALVE - The present invention is directed to remote operation of an operation valve such as an air operated valve even at the time of power loss. A gas supply apparatus of the present invention includes: an operation valve mounted in some midpoint of a piping for passing at least gas in a plant and operating a valve body by the gas flowing in the piping; an solenoid valve mounted in some midpoint of the piping and allowing/stopping flow of the gas to the operation valve; and a gas supply source for supplying gas to the solenoid valve. A switching valve for switching between exhaust from the solenoid valve and gas supply to the solenoid valve is mounted in an exhaust line of the solenoid valve and, at the time of power loss, the switching valve is switched to connection to the gas supply source for supplying gas to the solenoid valve. | 09-11-2014 |
20140233689 | Water Jet Peening Apparatus and Water Jet Peening Method - In a water jet peening apparatus, a high-pressure under-water pump is installed on an upper end of a casing and an injection nozzle drive mechanism equipped with an injection nozzle is attached to the casing. A high-pressure hose whose one end is connected to the high-pressure under-water pump is disposed in the casing and the other end of the high-pressure hose is connected to the injection nozzle. The casing is seated at an upper end of a control rod drive mechanism housing and the high-pressure under-water pump is driven. The high-pressure water pressurized by the high-pressure under-water pump is supplied to the injection nozzle through the high-pressure hose in the casing and is jetted toward the weld portion between the control rod drive mechanism housing and a stub tube. The time required for a water jet peening operation can be shortened. | 08-21-2014 |
20140230585 | Gap Expanding Method of Ball Screw and Fine Motion Control Rod Drive Mechanism Incorporating Gap Expanded Ball Screw - It is an object of the present invention to provide a gap expanding method of a ball screw for preventing an increase in torque relative to an electric motor due to a protruding bulge caused by generation of a scar on the traveling side of the screw shaft of the ball screw, and to provide a control rod drive mechanism incorporating the gap expanded ball screw. In a ball screw disposed in a control rod drive mechanism, the ball screw has a screw shaft and a ball nut engaged with the screw shaft via travelling balls, and the balls are each configured to have a diameter smaller than that of the existing ball, thereby expanding a gap between a ball traveling side of the screw shaft and the ball and a gap between the ball and a ball traveling side of the ball nut. | 08-21-2014 |
20140210988 | Inspection Apparatus and Method for Producing Image for Inspection - In order to obtain a quality image without deterioration owing to radiation noise in inspection using the optical video camera in high radiation environment, an inspection apparatus is formed of an image pick-up unit, an image obtaining unit which fetches a video image that contains a signal (noise) that is substantially independent of each frame obtained by the image pick-up unit, a local alignment unit which locally aligns frames with different time phases for forming the image fetched by the image obtaining unit, a frame synthesizing unit which synthesizes the plurality of frames aligned by the local alignment unit for generating a synthesis frame with an SN ratio higher than the SN ratio of the frame before frame synthesis, and an image output unit for displaying or recording the image formed of the synthesis frame generated by the frame synthesizing unit. | 07-31-2014 |
20140178282 | Radionuclide Adsorbent, Method of Producing Radionuclide Adsorbent and Production Apparatus Thereof - Granular crystalline silicotitanate (CST) is supplied from an adsorbent raw material supply apparatus into a caustic treatment apparatus. A sodium hydroxide solution of 1 Mol/L in a caustic agent supply apparatus is supplied into the caustic treatment apparatus with the granular CST supplied. After a predetermined quantity of the sodium hydroxide solution is supplied to the caustic treatment apparatus, the supply of the sodium hydroxide solution to the caustic treatment apparatus is stopped. The granular CST is left to stand for 0.5 hour in the state that it is immersed in the sodium hydroxide solution in the caustic treatment apparatus and is subjected to the caustic treatment. After that, the granular CST subjected to the caustic treatment is cleaned by cleaning water in a cleaning water supply apparatus. The respective adsorptive performances of cesium and strontium of the granular CST subjected to the caustic treatment are improved more. | 06-26-2014 |
20140140465 | Platinum Oxide Colloidal Solution, Manufacturing Method Therefor, Manufacture Apparatus Thereof, and Method of Injection Noble Metal of Boiling Water Nuclear Power Plant - An aqueous solution of alkali hexahydroxo platinate is produced. As a alkali hexahydroxo platinate, sodium hexahydroxoplatinate or potassium hexahydroxoplatinate is used. The aqueous solution of alkali hexahydroxo platinate is passed through a hydrogen form cation exchange resin layer in a cation exchange resin tower. The aqueous solution of alkali hexahydroxo platinate makes contact with the hydrogen form cation exchange resin of the hydrogen form cation exchange resin layer, thus a suspension of hexahydroxo platinic is generated. If gamma rays are irradiated to the suspension, a platinum oxide colloidal solution in which colloidal particles including a platinum dioxide, a platinum monoxide, and a platinum hydroxide exist is generated. In a platinum oxide colloidal solution, the content of impurities is little and a noble metal compound is dispersed stably in water. | 05-22-2014 |
20140112426 | Passive Residual Heat Removal System and Nuclear Power Plant Equipment - The invention includes a heat exchanger provided at a position higher than a primary containment vessel; a condensate storage tank disposed below the heat exchanger and above an upper end of a reactor core placed in a reactor pressure vessel; a non-condensate gas discharge line connected to an upper section of the condensate storage tank and to a suppression pool; a second condensate discharge line connected to a position below that section of the condensate storage tank to which a first end of the non-condensate gas discharge line is connected, and to the suppression pool; and a condensate return line connected to a position below that section of the condensate storage tank to which a first end of the second condensate discharge line is connected, and to a side portion of the reactor pressure vessel, the side portion being above the upper end of the core. | 04-24-2014 |
20140069810 | Electrochemical Corrosion Potential Sensor - An electrochemical corrosion potential sensor has a sensor unit, a lead wire and a quasi-reference electrode. A sensor unit includes a tube-shaped insulator, a tube-shaped metal casing joined to an end portion of the insulator, and a Pt electrode joined to another end portion of the insulator. A lead wire connected to the Pt electrode passes through the insulator and the metal casing. The quasi-reference electrode disposed in the metal casing is made of a less noble metal and electrically connected with the lead wire. | 03-13-2014 |
20140064433 | Fuel Assembly and Core of Nuclear Reactor - In a fuel assembly having fuel rods U | 03-06-2014 |
20140064427 | GAS TREATMENT EQUIPMENT OF NUCLEAR POWER PLANT - At the time of loss of coolant accident, when station blackout occurs, hydrogen, radioactive nuclides, and steam are discharged from a broken portion of a pipe connected to a reactor pressure vessel into the primary containment vessel. A passive autocatalytic hydrogen treatment apparatus installs a catalytic layer and heat exchanger tubes of a heat exchanger in a casing. High-temperature steam including hydrogen and radioactive nuclides is supplied into the heat exchanger tubes and heats gas supplied into the casing | 03-06-2014 |
20140037039 | Fuel Assembly and Reactor Core - A fuel assembly with a plurality of fuel rods, extending along a uniform direction, disposed inside a channel box assuming a quadrangular duct shape, wherein: the plurality of fuel rods that are disposed on sides of a plurality of hypothetical concentric quadrangles of various sizes with shapes similar to a cross-sectional shape of the channel box viewed from an end along which the fuel rods extend, and include at least outermost fuel rods disposed on the sides of a largest hypothetical concentric quadrangle among the hypothetical concentric quadrangles and second layer fuel rods disposed on the sides of a second largest hypothetical concentric quadrangle among the hypothetical concentric quadrangles; and the outermost fuel rods are disposed so that consecutive outermost fuel rods are set apart from each other over equal intervals which are greater than intervals setting apart consecutive fuel rods among the second layer fuel rods. | 02-06-2014 |
20140037037 | Method of Depositing Noble Metal on Structure Member of Nuclear Plant - A noble metal injection apparatus is connected to a piping of a nuclear plant at the time of stop of the nuclear plant before start of the nuclear plant. In chemical decontamination, oxidation decontamination agent decomposition, and reduction decontamination on an inner surface of the pipe system are executed. After reduction decontamination, a part of an oxalic acid included in a reduction decontamination solution is decomposed and platinum is injected into the reduction decontamination solution of pH 3.5 or higher. When the platinum concentration becomes a preset concentration, a reduction agent is injected and the reduction decontamination solution including the platinum and reduction agent is brought into contact with the inner surface of the piping. The platinum is deposited on the inner surface of the piping. The injection of the platinum and reduction agent is stopped and the platinum and reduction agent are decomposed. | 02-06-2014 |
20130223581 | Nuclear Power Plant - When a power source is lost after an operation stop of a nuclear power plant, a first open/close valve is opened via a first battery at an early stage and steam in a reactor pressure vessel (RPV) is condensed in a suppression pool. The heat of the water in the suppression pool is transmitted to a cooling water pool located below inner space between first and second reactor containment vessels surrounding the RPV. A second open/close valve is opened via a second battery at the early stage and cooling water in a tank is injected into the RPV. After the early stage, a third open/close valve is opened via a third battery, and a cooling medium becomes steam by an evaporator in the RPV, the steam being condensed by a condenser disposed in the inner space to become a liquid of the cooling medium and is returned to the evaporator. | 08-29-2013 |
20130202791 | Suppression Method for Corrosion of Carbon Steel Member - A bath containing nickel ions and formic acid is injected into a film-forming aqueous solution flowing in a circulation pipe connected to a feed water pipe made of carbon steel in a BWR plant. This solution is supplied into the pipe through the circulation pipe, and a nickel metal film is formed on an inner surface of the pipe. After the film is formed, a film-forming aqueous solution containing iron (II) ions, formic acid, nickel ions, hydrogen peroxide, and hydrazine is supplied to the pipe. A nickel ferrite film is formed on the surface of the nickel metal film in the pipe. The nickel ferrite film comes into contact with water containing dissolved oxygen at or above 150° C. to transform the nickel metal film into a nickel ferrite film. A thick nickel ferrite film is formed on the inner surface of the feed water pipe. | 08-08-2013 |
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 |
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 |
20130193960 | Eddy Current Flaw Detection System and Eddy Current Flaw Detection Method - An eddy current flaw detection system includes an eddy current flaw detection probe having a substrate facing an inspection surface, and at least one exciting coil and at least two detecting coils provided on the substrate, a scanning device which scans the probe on the inspection surface, a scan control device which drives and controls the scanning device, an eddy current flaw detection device which acquires results of detection of a plurality of detection points corresponding to combinations of the exciting and detecting coils for each scan position of the probe, and a data processing/display device which processes data from the scan control device and the eddy current flaw detection device and thereby displays a result of flaw detection. The data processing/display device acquires three-dimensional coordinates of the detection points for each scan position of the probe and thereby creates three-dimensional flaw detection data. | 08-01-2013 |
20130182811 | Method of Monitoring Reactor Bottom Area, Reactor Bottom Area Monitoring Apparatus and Nuclear Reactor - An ultrasonic sensor has a piezo-electric element attached at an end surface outside a reactor pressure vessel (RPV) of a sensor leading edge portion. The sensor leading edge portion passes through a bottom head of the RPV and is installed on the bottom head. Ultrasonic waves generated by the piezo-electric element are propagated to the sensor leading edge portion and are propagated to reactor water in the RPV from the sensor leading edge portion. When water surface of the reactor water in the RPV exists below a core support plate, the ultrasonic waves propagated inside the reactor water are reflected on the water surface. Ultrasonic waves reflected on the water surface are propagated into the reactor water, enter the sensor leading edge portion, and are received by the piezo-electric element. Using the ultrasonic waves received by the piezo-electric element, the water level in the RPV is obtained. | 07-18-2013 |
20130177122 | Reactor Water-Level/Temperature Measurement Apparatus - A reactor water-level/temperature measurement apparatus is disclosed that includes an in-core instrumentation tube inserted into an in-core instrumentation housing and an in-core instrumentation guide tube, a plurality of water-level/temperature detection sensors provided in the tube, a temperature measurement device measuring the temperature of a thermocouple included in each of the sensors, a heater control device for controlling a current flowing to a heater wire included in each of the sensors, a storage device used for storing a threshold-value table, and a water atmosphere and a sensor failure and a water-level/temperature/failure determination device. | 07-11-2013 |
20130174637 | Ultrasonic Reactor Water Level Measuring Device and Evaluation Method - An ultrasonic reactor water level measuring device and an evaluation method are provided and prevent a reduction in the measurement accuracy of a water level that is in a wide measurement range. The ultrasonic reactor water level measuring device includes an upper tube extending from a gas phase portion in a reactor, a lower tube extending from a liquid phase portion in the reactor, measurement tubes connected to each other and arranged at multiple stages between the upper tube and the lower tube, and units for generating and receiving ultrasonic waves, the units being arranged at bottom portions of the measurement tubes. The ultrasonic reactor water level measuring device measures levels of water within the measurement tubes and calculates a water level within the reactor from the sum of the measured water levels, the sum excluding an overlapped part of the measurement tubes. | 07-11-2013 |
20130174627 | Method of Executing Water Jet Peening - A top head of a reactor pressure vessel is provided with a plurality of control rod drive mechanism (CRDM) penetration pipes arranged in a square grid-like pattern. The CRDM penetration pipes are joined by a tube support member disposed among them. The top head is placed on a tank and water is filled in an inner region of the tank and the top head. A travel apparatus moves a nozzle lifting/lowering apparatus to a predetermined location and a lifting/lowering mechanism is operated to lift a jet nozzle above the tube support member in the neighboring four CRDM penetration pipes. An ejection outlet of the jet nozzle is directed to a weld between one of the CRDM penetration pipes and the top head, and a water jet is ejected to start WJP. A nozzle turning mechanism turns the jet nozzle, and WJP is executed sequentially to the four CRDM penetration pipes. | 07-11-2013 |
20130149142 | Sliding Bearing and Pump Device Using the Same - In a sliding bearing, load carrying capacity and bearing rigidity is increased without increasing a size of the bearing and the pressure of the fluid. The sliding bearing comprises a cylindrical-shaped sleeve supporting a rotatable shaft via fluid, and hydrostatic pressure pockets provided in the inner periphery of the sleeve. The hydrostatic pressure pockets constitute a plurality of rows of circumferentially disposed hydrostatic pressure pockets via orifices. At least one of the hydrostatic pressure pocket rows is arranged adjacently to each of both end portions of the inner periphery of the sleeve. And a circular cylindrical inner peripheral surface region without the hydrostatic pressure pockets is provided at a center portion of the sleeve. A width of the circular cylindrical inner peripheral surface region provided in the axial direction of the shaft is made wider than a sum of widths of the hydrostatic pressure pocket rows. | 06-13-2013 |
20130125929 | Preventive Maintenance Apparatus and Preventive Maintenance Method for Inner Surface of Piping - A preventive maintenance apparatus has a movable body and a water jet peening apparatus (WJP apparatus). The movable body installs a jet nozzle for driving and floating bodies on a base body. The movable body suspended in cooling water in a reactor pressure vessel jets high-pressure water from a high-pressure pump from the jet nozzle, advances in the cooling water, and is inserted into a pipe with the cooling water filled which is connected to the reactor pressure vessel. The posture of the movable body in the pipe is controlled by buoyancy adjustment of the floating bodies and the movable body can easily pass through a curve pipe portion. The high-pressure water from a high-pressure pump is jetted from jet nozzles of the WJP apparatus and for the inner surface of a vertical pipe portion, the WJP is executed. | 05-23-2013 |
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 |
20130077730 | Nuclear Power Plant - A nuclear power plant has a reactor pressure vessel, a primary containment vessel and a passive pressure suppression pool cooling system. The reactor pressure vessel is installed in the primary containment vessel. A pressure suppression pool filled with cooling water is formed in a lower portion of the primary containment vessel. The passive pressure suppression pool cooling system is provided with a steam condensing pool in which cooling water is filled, disposed outside the primary containment vessel, a steam condenser disposed in the steam condensing pool, a steam supply pipe connecting the reactor pressure vessel to the steam condenser, and a condensed water discharge pipe connected to the steam condenser for discharging condensed water generated in the steam condenser. Another end portion of the condensed water discharge pipe is disposed in the pressure suppression pool. | 03-28-2013 |
20130051509 | Initial Core of Nuclear Reactor and Method of Loading Fuel Assemblies of Nuclear Reactor - In an initial core of a nuclear reactor, a plurality of water regions having a square cross section for occupying a cross sectional area capable of disposing four fuel assemblies are formed. No fuel assemblies are loaded in these water regions. In the initial core, each fuel assembly is supported by fuel supports. A pressure loss of a first orifice installed in a cooling water supply passage formed in first fuel supports disposed in a central portion of the initial core is larger than that of a second orifice installed in a cooling water supply passage formed in second fuel supports disposed in a peripheral portion surrounding the central portion. Each water region is formed right above a part of the first fuel supports disposed in the central portion. The control rod operation in the nuclear reactor can be simplified by action of cooling water in the water regions. | 02-28-2013 |
20120294407 | Nuclear Power Plant, Fuel Pool Water Cooling Facility and Method Thereof - A nuclear power plant and a fuel pool water cooling facility and method are provided that can suppress the decrease of a water level in a fuel pool with no power supply at the time of malfunction of a circulating water system. | 11-22-2012 |
20120291554 | Heat-Resistant Ultrasonic Sensor and Installation Method Thereof - A heat-resistant ultrasonic sensor forms a piezo-electric ceramics film with a thickness of 0.5 mm or smaller and a Curie point of 200° C. or higher on a flexible metal plate. A thin metal film that is an electrode is attached to a top surface of the piezo-electric ceramics film and a metal wire mesh covers the thin metal film and is attached to a top surface of the thin metal film. A core of a heat-resistant coaxial cable is connected to the metal wire mesh at a connection point. The heat-resistant coaxial cable is fixed to the thin metal plate with a metal fixing member that is a ground portion. An electric insulating cover is attached to the thin metal plate and covers the piezo-electric ceramics film, the thin metal film, the metal wire mesh, the connection point, the fixing member, and the core of the coaxial cable. | 11-22-2012 |
20120281800 | Method of Checking Installed State of Jet Pump Beam - A jet pump beam (hereinafter, referred to as a beam) is fitted into a pair of projecting portions installed to a transition piece, and after the beam is arched, a beam bolt engaged with the beam is tightened. An end of the beam bolt comes in contact with a top surface of an insert member fitted into an elbow disposed between the pair of projecting portions. An ultrasonic sensor head is fixed to the beam bolt, and ultrasonic waves are sent to the beam bolt from the ultrasonic sensor in the ultrasonic sensor head. An ultrasonic measuring apparatus obtains echo intensity of each of reflected waves generated at the end of the beam bolt and a bottom surface of the insert member, and based on the echo intensities, an echo intensity ratio R is calculated. The installed state of the beam is checked using the echo intensity ratio R. | 11-08-2012 |
20120140866 | FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM - A fast breeder reactor type nuclear power plant system including a reactor vessel provided with a core and a pipe of primary loop coolant for supplying primary loop coolant to the reactor vessel. One or more bending parts are formed on at least the pipe of primary loop coolant of the pipes, and a part of the bending part on a downstream side is provided with a flow path having a non-circular sectional configuration wherein the negative side of the bending part is formed in either a planar or flat shape. | 06-07-2012 |
20120026317 | Inspection Apparatus and Method for Producing Image for Inspection - In order to obtain a quality image without deterioration owing to radiation noise in inspection using the optical video camera in high radiation environment, an inspection apparatus is formed of an image pick-up unit, an image obtaining unit which fetches a video image that contains a signal (noise) that is substantially independent of each frame obtained by the image pick-up unit, a local alignment unit which locally aligns frames with different time phases for forming the image fetched by the image obtaining unit, a frame synthesizing unit which synthesizes the plurality of frames aligned by the local alignment unit for generating a synthesis frame with an SN ratio higher than the SN ratio of the frame before frame synthesis, and an image output unit for displaying or recording the image formed of the synthesis frame generated by the frame synthesizing unit. | 02-02-2012 |
20110308316 | NONDESTRUCTIVE INSPECTION APPARATUS AND NONDESTRUCTIVE INSPECTION METHOD USING GUIDED WAVE - A nondestructive inspection apparatus includes a pair of guided wave sensors disposed on an outer surface of a piping and a guided wave inspection device connected to the pair of guided wave sensors which, outputs a transmitting signal for propagating a guided wave to the guided wave sensors, and obtains a receiving signal by receiving a propagated signal by the guided wave sensors. An inspection-result storage device stores the guided wave as a digitized signal of the received wave and an inspection-result diagnostic device performs arithmetic processing of judging whether or not a signal associated with a defect exists. | 12-22-2011 |
20110286569 | FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM - A fast breeder reactor type nuclear power plant system including a reactor vessel provided with a core and a pipe of primary loop coolant for supplying primary loop coolant to the reactor vessel. One or more bending parts are formed on at least the pipe of primary loop coolant of the pipes, and a part of the bending part on a downstream side is provided with a flow path having a non-circular sectional configuration wherein the negative side of the bending part is formed in either a planar or flat shape. | 11-24-2011 |
20110286568 | Boiling Water Nuclear Plant and Method of Reducing Dose in Turbine System - An adsorbing substance made of a material having an acid center in its molecular frame is installed in a passage for steam generated in a reactor pressure vessel | 11-24-2011 |
20110277304 | Method of Forming Ferrite Film on Structural Member Composing Plant - Both ends of a circulation pipe of a film formation apparatus are connected to a piping of a BWR plant. A chemical including chromium ions and formic acid is injected into a film formation solution flowing in the circulation pipe heated to a temperature within a range from 60° C. to 100° C. Furthermore, a chemical including iron (II) ions and formic acid, hydrogen peroxide, and hydrazine are injected into the circulation pipe. Due to the injection of these chemicals, a film formation solution of pH 7.0 including iron (II) ions, chromium ions, formic acid, hydrogen peroxide, and hydrazine is generated in the circulation pipe. This film formation solution includes hydrazine of, for example, 1000 ppm. The film formation solution is supplied to the piping, thus, a Fe | 11-17-2011 |
20110268242 | Hydrogen and Oxygen Recombination Catalyst, Recombination Apparatus, and Nuclear Plant - A recombination apparatus is provided to an off-gas system of a boiling water nuclear plant. An off-gas system pipe connected to a condenser is connected to the recombination apparatus. A catalyst layer filled with a catalyst for recombining hydrogen and oxygen is disposed in the recombination apparatus. The recombination catalyst has a percentage of the number of Pt particles whose diameters are in a range from more than 1 nm to not more than 3 nm to the numbers of Pt particles whose diameters are in a range from more than 0 nm to not more than 20 nm, falling within a range from 20 to 100%. The condenser discharges gas containing an organosilicon compound (ex. D5), hydrogen, and oxygen, which is introduced to the recombination apparatus. Use of the above recombination catalyst can improve the performance of recombining hydrogen and oxygen more than conventional catalysts and the initial performance of the catalyst can be maintained for a longer period of time. | 11-03-2011 |
20110216872 | Boiling Water Nuclear Plant and Steam Dryer - In the boiling water nuclear plant of the present invention, a steam dryer is disposed in a reactor pressure vessel. Materials that have capability of capturing nitrogen compounds containing N-16 are supported on porous member. The porous members are placed in a region where steam goes through in the steam dryer. For example, both or either of perforated plates installed in the steam dryer is constituted of the porous member on which N-16 capture material is supported. When steam containing N-16 goes through the perforated plates, the N-16 is captured by the porous member, whereby the N-16 transfer amount into the turbine system is reduced. | 09-08-2011 |
20110204871 | Core Recognition System and Core Recognition Method - An object of the invention is to prevent a human error, greatly reducing man-hours and to securely identify a core. To achieve the object, a request for a serial number is first made via a conductor of a core from a recognition unit that functions as a master to a recognition unit that functions as a slave. Next, the recognition unit as the slave reads a serial number for an IC tag and transmits the serial number via the conductor of the core. The recognition unit as the master receives the serial number transmitted from the recognition unit as the slave and collates the serial number and a serial number stored in an IC tag. It is ascertained by the collation that the conduction of the core is correctly made and it is displayed on a display of the recognition unit as the master and others that no disconnection on the way and no error in selecting an end of wiring are caused. | 08-25-2011 |
20110197679 | ULTRASONIC INSPECTION SYSTEM AND ULTRASONIC INSPECTION METHOD - In an ultrasonic inspection method or ultrasonic inspection system in which an ultrasonic wave is propagated to an test object via a medium such as a liquid or a gas, an incident position of the ultrasonic wave is accurately and reliably identified. In an ultrasonic inspection method based on an immersion technique, an optical irradiator is mounted on an ultrasonic wave transmitting/receiving unit, an optical marker is irradiated from the optical irradiator to the test object, and an irradiated position of the optical marker is imaged using imaging equipment in order to perform inspection. | 08-18-2011 |
20110176649 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 07-21-2011 |
20110166807 | ULTRASONIC INSPECTION METHOD AND ULTRASONIC INSPECTION DEVICE - An ultrasonic inspection method and an ultrasonic inspection device allow three-dimensional inspection data and three-dimensional shape data to be appropriately positioned on a display screen and allow a defect echo and a shape echo to be quickly identified even when information on the relative positions of a probe and an object to be inspected is not provided. The ultrasonic inspection data that is generated from the waveforms of ultrasonic waves received by an ultrasonic probe is compared with a plurality of ultrasonic propagation data pieces calculated by a ray tracing method on the basis of the three-dimensional shape data on an object to be inspected. The position of the three-dimensional inspection data or the three-dimensional shape data is moved relative to the other data position on the basis of the comparison results, thereby displaying the three-dimensional inspection data and the three-dimensional shape data while overlapping each other. | 07-07-2011 |
20110126625 | Ultrasonic Measurement Method, Ultrasonic Measurement Apparatus, and Ultrasonic Sensor - An ultrasonic measurement method and an ultrasonic measurement apparatus are capable of performing an inspection for a short time with a high SN ratio and a small variation (that depends on an inspection direction) in sensitivity in a process for detecting a defect in all directions at 360 degrees using a matrix array sensor without performing mechanical scanning in all directions, while reducing noise that is caused by a bottom surface echo. An element selecting circuit selects a group of a plurality of ultrasonic transducer elements for transmission from among ultrasonic transducer elements that constitute a two-dimensional array sensor so that the ultrasonic transducer elements for selected for transmission are arranged in line symmetry with respect to a first line symmetric axis to set the group selected for transmission. The element selecting circuit selects a group of a plurality of ultrasonic transducer elements for reception so that the ultrasonic transducer elements selected for reception are arranged in line symmetry with respect to a second line symmetric axis that is perpendicular to the first line symmetric axis to set the group selected for reception. A transmitting element selector selects, as transmitting elements, the ultrasonic transducer elements set by the element selecting circuit. A receiving element selector selects, as receiving elements, the ultrasonic transducer elements set by the element selecting circuit. | 06-02-2011 |
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 |
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 |
20110030850 | Suppression Method for Corrosion of Carbon Steel Member - A bath containing nickel ions and formic acid is injected into a film-forming aqueous solution flowing in a circulation pipe connected to feed water pipe made of carbon steel in a BWR plant. This film-forming aqueous solution is supplied into the feed water pipe through the circulation pipe, and then, a nickel metal film is formed on an inner surface of the feed water pipe. After the nickel metal film is formed, a film-forming aqueous solution containing iron (II) ions, formic acid, nickel ions, hydrogen peroxide, and hydrazine is supplied to the feed water pipe. A nickel ferrite film is formed on the surface of the nickel metal film in the feed water pipe. Then, the nickel ferrite film is come into contact with water containing dissolved-oxygen at 150° C. or above to transform the nickel metal film into a nickel ferrite film. A thick nickel ferrite film is formed on the inner surface of the feed water pipe. Corrosion of the carbon steel member composing the plant can further reduce. | 02-10-2011 |
20110005288 | Water Jet Peening Method and Apparatus Thereof - A high-pressure water jet is injected from a nozzle scanned and a shock wave generated due to the collapse of bubbles included in the water jet is impacted on a WJP execution object. Tensile residual stress close to the surface of the WJP execution object is improved to compressive residual stress. The shock wave is detected by a pressure sensor and a shock wave generation frequency is obtained. Whether the obtained shock wave generation frequency is larger than a set value or not is decided. When the shock wave generation frequency is larger than the set value, a high-pressure pump is stopped and the injection of the water jet from the nozzle is stopped. When the shock wave generation frequency is equal to or smaller than the set value, the operation condition of the high-pressure pump is changed. The pressure of the water jet injected from the nozzle is increased and the WJP is executed for a part of the WJP execution object where the shock wave generation frequency is equal to or smaller than the set value. Improvement effect of the residual stress of the WJP execution object can be confirmed more accurately. | 01-13-2011 |
20110005225 | Electric Power Plant, and Method for Running Electric Power Plant - An electric power plant, e.g., a boiling water reactor nuclear power plant supplies steam generated in a nuclear reactor to a high-pressure turbine and a low-pressure turbine. The steam discharged from the low-pressure turbine is condensed with a condenser. Water generated with the condenser, used as feed water, flows through a feed water pipe, is heated with a low-pressure feed water heater and a high-pressure feed water heater, and then supplied to the nuclear reactor. The steam extracted from the high-pressure turbine is supplied to the high-pressure feed water heater. The steam extracted from the low-pressure turbine is compressed with a steam compressor, and the steam whose temperature has been increased is then supplied to the high-pressure feed water heater. The feed water to be directed to the nuclear reactor is heated in the high-pressure feed water heater by both the steam extracted from the high-pressure turbine and the steam compressed with the steam compressor. Because the feed water is heated by both the extracted steam and the compressed steam in the high-pressure feed water heater, the amount of plant service power consumed by the steam compressor can be reduced. Therefore, it is possible to increase thermal efficiency in the electric power plant when increasing the power output. | 01-13-2011 |
20100251821 | Ultrasonic Measurement Method, Ultrasonic Measurement Apparatus, and Ultrasonic Sensor - An ultrasonic measurement method and an ultrasonic measurement apparatus are capable of performing an inspection for a short time with a high SN ratio and a small variation (that depends on an inspection direction) in sensitivity in a process for detecting a defect in all directions at 360 degrees using a matrix array sensor without performing mechanical scanning in all directions, while reducing noise that is caused by a bottom surface echo. An element selecting circuit selects a group of a plurality of ultrasonic transducer elements for transmission from among ultrasonic transducer elements that constitute a two-dimensional array sensor so that the ultrasonic transducer elements for selected for transmission are arranged in line symmetry with respect to a first line symmetric axis to set the group selected for transmission. The element selecting circuit selects a group of a plurality of ultrasonic transducer elements for reception so that the ultrasonic transducer elements selected for reception are arranged in line symmetry with respect to a second line symmetric axis that is perpendicular to the first line symmetric axis to set the group selected for reception. A transmitting element selector selects, as transmitting elements, the ultrasonic transducer elements set by the element selecting circuit. A receiving element selector selects, as receiving elements, the ultrasonic transducer elements set by the element selecting circuit. | 10-07-2010 |
20100226541 | SYSTEM AND METHOD FOR DETECTING POSITION OF UNDERWATER VEHICLE - An object of the invention is to provide a system for detecting the position of an underwater vehicle that enables an improvement in the accuracy of detecting the position of the underwater vehicle. | 09-09-2010 |
20100206729 | ELECTROCHEMICAL CORROSION POTENTIAL SENSOR - An electrochemical corrosion potential sensor (ECP sensor) has an electrode cap, an electrode fixing body, a tubular insulator, a tubular metallic housing, and a conductive wire. Both ends of the tubular insulator are connected to the electrode fixing body and the tubular metallic housing respectively. A conductive wire passes through the tubular insulator and the tubular metallic housing, and is connected to an inner surface of the electrode fixing body. The electrode cap | 08-19-2010 |
20100136215 | METHOD FOR FORMING FERRITE FILM ONTO SURFACE OF STRUCTURAL MEMBER COMPOSING PLANT, FERRITE FILM FORMATION APPARATUS AND QUARTZ CRYSTAL ELECTRODE APPARATUS - A method for forming a ferrite film onto surface of structural member composing a plant, comprises steps of forming a ferrite film onto the wetted surface of the structural member by making contact with a film forming solution containing iron (II) ions, an oxidant for oxidizing the iron (II) ions, and a pH adjustment agent; measuring the amount of the formed ferrite film; and determining completion of the ferrite film formation based on the measured amount of the formed ferrite film. The method for forming the ferrite film onto the surface of the structural member, can shorten the time required for completing the ferrite film forming operations. | 06-03-2010 |
20100114635 | CONSTRUCTION PROGRESS VISUALIZATION SYSTEM AND METHOD OF VISUALIZING CONSTRUCTION PROGRESS - A construction progress visualization system, comprising of a scaffolding model creating-unit for creating an area and a form of scaffolding required for a construction operation based on a 3D CAD model and a construction schedule data; a scaffolding schedule extracting-unit for extracting scaffolding schedule data regarding the scaffolding from the construction schedule data; a scaffolding display form determining-unit for determining a completion rate of the scaffolding on a visualization-target date based on a relationship between the visualization-target date and the scaffolding schedule data, and obtaining a display form of the scaffolding; and a display process unit for displaying, concurrently with the CAD model, the scaffolding area based on the obtained display form of the scaffolding. | 05-06-2010 |
20090185653 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant and Ferrite Film Formation Apparatus - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 07-23-2009 |
20090141849 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant and Ferrite Film Formation Apparatus - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 06-04-2009 |
20090003509 | Suppression Method of Radionuclide Deposition on Reactor Component of Nuclear Power Plant and Ferrite Film Formation Apparatus - A method of suppressing deposition of radionuclides on components of a nuclear power plant comprises forming a ferrite film by contacting a first chemical including iron (II) ions, a second chemical for oxidizing the iron (II) ions to iron (III) ions, and a third chemical for adjusting the pH of a processing solution containing a mixture of the first and second chemicals to be 5.5 to 9.0 with the metal member surface in a time period from a finishing stage in decontamination step of removing contaminants formed on the surface of metal member composing the nuclear power plant, and suppressing deposition of radionuclides on the metal member by the ferrite film. | 01-01-2009 |