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Небесная энциклопедия

Космические корабли и станции, автоматические КА и методы их проектирования, бортовые комплексы управления, системы и средства жизнеобеспечения, особенности технологии производства ракетно-космических систем

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Мониторинг СМИ

Мониторинг СМИ и социальных сетей. Сканирование интернета, новостных сайтов, специализированных контентных площадок на базе мессенджеров. Гибкие настройки фильтров и первоначальных источников.

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Форма поиска

Поддерживает ввод нескольких поисковых фраз (по одной на строку). При поиске обеспечивает поддержку морфологии русского и английского языка
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Применить Всего найдено 4224. Отображено 200.
09-09-1993 дата публикации

Konvergenzvorrichtung

Номер: DE0003903277C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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05-08-1993 дата публикации

Kompressoranlage

Номер: DE0003836643C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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09-09-1993 дата публикации

Kraftstoffeinspritzanlage für eine Brennkraftmaschine mit mehreren Zylindern

Номер: DE0002952962C3
Принадлежит: Hitachi

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08-04-1993 дата публикации

Integrierte Halbleiterschaltungsanordnung

Номер: DE0003233632C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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24-03-1994 дата публикации

Elektrophoresegerät

Номер: DE0004139211C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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19-05-1993 дата публикации

Differenzdruckwertgeber

Номер: DE0003928426C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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07-07-1994 дата публикации

Massenspektrometer

Номер: DE0003913763C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO

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08-09-1994 дата публикации

Automatisches Analysegerät für klinische Untersuchungen

Номер: DE0004231172C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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09-06-1994 дата публикации

Flüssigkeitsstandanzeiger

Номер: DE0004033988C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO

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23-09-1993 дата публикации

Starter für eine Brennkraftmaschine

Номер: DE0004117681C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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11-11-1993 дата публикации

Schmierungsfreie Rotationskolbenmaschine in Schraubenbauweise

Номер: DE0003911020C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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05-08-1993 дата публикации

Massenspektrometer für Spurenelemente

Номер: DE0003940900C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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01-12-1994 дата публикации

Photometer

Номер: DE0004005670C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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08-04-1993 дата публикации

Abgasturbolader für Brennkraftmaschinen

Номер: DE0003833906C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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02-09-1993 дата публикации

Verfahren und Vorrichtung zur Fourier-Spektrophotometrie

Номер: DE0003900247C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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17-11-1994 дата публикации

Steuervorrichtung für ein Bildschirmgerät

Номер: DE0003419219C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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02-09-1993 дата публикации

Vorrichtung zum automatischen Ansaugen und Ausgeben von Flüssigkeitsportionen

Номер: DE0004113377C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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14-10-1993 дата публикации

Anlasser für eine Brennkraftmaschine

Номер: DE0003828878C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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08-07-1993 дата публикации

Axialkolbenpumpe

Номер: DE0004105092C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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20-01-1994 дата публикации

Halbleiteranordnung mit Schutzmetalleinrichtung

Номер: DE0003331624C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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17-06-1993 дата публикации

Massenspektrometer mit Atmosphärendruck-Ionisation

Номер: DE0003636954C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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05-08-1993 дата публикации

Luftströmungsmesser für Verbrennungsmotor und Herstellungsverfahren für einen solchen Luftströmungsmesser

Номер: DE0009116731U1
Автор:
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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27-10-1994 дата публикации

Absorptionsphotometer

Номер: DE0003724852C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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18-03-1993 дата публикации

Integrierte Halbleiterschaltung

Номер: DE0003519249C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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23-12-1993 дата публикации

Feldsensor-Kommunikationssystem

Номер: DE0004021258C2
Принадлежит: HITACHI LTD, HITACHI, LTD., TOKIO/TOKYO, JP

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06-05-1993 дата публикации

Strahlengang-Justiereinrichtung

Номер: DE0003940694C2
Принадлежит: HITACHI, LTD., TOKIO/TOKYO, JP

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02-02-2012 дата публикации

Inspection Apparatus and Method for Producing Image for Inspection

Номер: US20120026317A1
Автор:
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. An inspection apparatus comprising:an image pick-up unit provided with an optical video camera;an image obtaining unit which fetches a video image that contains a signal (noise) that is substantially independent of each frame of the video image obtained by picking up a video image of an inspection object by the image pick-up unit;a local alignment unit which locally aligns a plurality of frames of the video image with different time phases;a frame synthesizing unit which synthesizes the plurality of frames of the video image aligned by the local alignment unit for generating an image formed of the synthesized frames with an SN ratio higher than the SN ratio of each of the frames before frame synthesis; andan image output unit for displaying or recording an image formed of the synthesis frame generated by the frame synthesizing unit.2. The inspection apparatus according to claim 1 , wherein the signal (noise) that is substantially independent of each frame contained in the video image picked up by the optical video camera is a radiation noise.3. The inspection apparatus according to claim 1 ,wherein the ...

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01-03-2012 дата публикации

WELDED PORTION INSPECTION APPARATUS OF REACTOR PRESSURE VESSEL

Номер: US20120051483A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

A welded portion inspection apparatus of a reactor pressure vessel moves on an outside surface of the reactor pressure vessel, and is provided with a scan portion having a sensor for detecting a state of the welded portion to be inspected. The apparatus has a first scan axis with a pedestal having the sensor installed for moving the sensor in a predetermined first direction to perform scanning, and a second scan axis orthogonal to the first scan axis for moving the first scan axis in a predetermined second direction. Drive portions are installed removably on both sides of the scan portion for moving the scan portion to a position of the welded portion to be inspected, and a motor is provided for driving the drive portions. The drive portions include a plurality of magnets which are endlessly formed in a line. 1. A welded portion inspection apparatus of a reactor pressure vessel comprising:a frame for moving on an outside surface of a reactor pressure vessel, which is provided with a scan portion having a sensor for detecting a state of a welded portion to be inspected, a first scan axis with a pedestal having the sensor installed for moving the sensor in a predetermined first direction to perform scanning, a second scan axis arranged in an orthogonal direction to the first scan axis for moving the first scan axis in a predetermined second direction, a first drive guidance portion installed in the first scan axis for moving the first scan axis with a pedestal having the sensor installed along the second scan axis, and a second drive guidance portion installed in the pedestal for moving the pedestal having the sensor along the first scan axis, anddrive portions installed removably on both sides of the scan portion for moving the scan portion to a position of the welded portion to be inspected, and a motor for driving the drive portions,wherein the drive portions are comprising a plurality of magnets which are endlessly formed in a line.2. The welded portion inspection ...

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19-04-2012 дата публикации

Lithium ion rechargeable batteries & the additive for lithium ion rechargeable batteries which prevents increase of the viscosity

Номер: US20120091403A1
Принадлежит: Hitachi Maxell Energy Ltd

The preparation of a slurry so as to exhibit no strong alkalinity not only needs a strict pH control, but also needs once dispersing a positive electrode material in water and the operation of drying after the treatment, and other operations, thereby leading to the complication of the operations and a decrease in the yield. In consideration of the above-mentioned problems, the present invention provides a method for producing a positive electrode plate for a lithium ion rechargeable battery, which exhibits less complication of the operations and less decrease in the yield and can prevent the gelation of a positive electrode material slurry. The above-mentioned problems can be solved by a positive electrode for a lithium ion rechargeable battery containing a positive electrode active material capable of absorbing/desorbing lithium ions, a nitrile group-containing polymer, and a binder.

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07-06-2012 дата публикации

FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM

Номер: US20120140866A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1a reactor vessel provided with a core;a pipe of primary loop coolant for supplying primary loop coolant to said reactor vessel;an intermediate heat exchanger for exchanging heat of said primary loop coolant;a primary loop recirculation pump for supplying said primary loop coolant to said reactor vessel and attached to said pipe of primary loop coolant;a pipe of secondary loop coolant for circulating said secondary loop coolant through said intermediate heat exchanger;a secondary loop recirculation pump for supplying said secondary loop coolant to said intermediate heat exchanger and attached to said pipe of secondary loop coolant;a steam generator for exchanging heat using said secondary loop coolant and heating water to generate steam;a main steam pipe for supplying said steam to turbine; anda feed water pipe for supplying feed water, which is water generated by condensing said steam exhausted from said turbine by a condenser, to said steam generator,wherein one or more bending parts are formed on at least said pipe of primary loop coolant of the pipes, and a part of said bending part on downstream side is provided with a flow path having a non-circular sectional configuration wherein the negative side of said bending part is formed in either a planar or flat shape,wherein a sectional configuration of a flow path formed on part of said bending part on the downstream side is one of oblong, spheroidal, square and rectangular.. A fast breeder reactor type nuclear ...

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09-08-2012 дата публикации

Twin-clutch type hybrid transmission

Номер: US20120203412A1
Принадлежит: Hitachi Nico Transmission Co Ltd

A twin-clutch type hybrid transmission is configured to include an input shaft 10 , an odd-numbered stage shift mechanism 30 , an even-numbered stage shift mechanism 60 , a motor power mechanism 20 , and an output mechanism 90 . The shift mechanisms 30 and 60 include transmission gear trains 32 and 62 , and main clutches 34 and 64 , respectively, the main clutches 34 and 64 for selectively transmitting the power of the transmission gear train 32 and the power of the transmission gear train 62 to transmission shafts 40 and 70 , respectively. The shift mechanisms 30 and 60 also include shift gear trains 41, 43, 45, 47, 72, 74, 76 , and 78 provided to the transmission shafts 40 and 70 to transmit rotation to the output mechanism 90 , respectively, and mechanical clutches 50, 52, 80 , and 82 for selectively engaging the corresponding shift gear trains and the transmission shafts 40 and 70 , respectively. As a result, a compact twin-clutch type hybrid transmission having high transmission efficiency can be obtained.

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01-11-2012 дата публикации

Object Recognition Method and Recognition Apparatus

Номер: US20120274782A1

A target fish-eye image for object recognition is split into regions in accordance with the distortion direction. An object recognition portion performs object recognition by using databases prepared in accordance with the regions respectively. The same process is applied to a plurality of target fish-eye images created by rotation of the target fish-eye image. A detected coordinate transformation portion restores the obtained position of an object into the original position by inverse rotation, and outputs a thus obtained result as a detection result. Detection accuracy in object recognition is improved, and the quality of data in databases is reduced. Rotated object images required for database creation are used for creation of databases for object recognition for the fish-eye image. Thus, a distorted fish-eye image for object recognition is directly used without projective conversion or image conversion based on corrective operation to the fish-eye image.

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08-11-2012 дата публикации

Method of Checking Installed State of Jet Pump Beam

Номер: US20120281800A1
Автор:
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A method of checking an installed state of a jet pump beam , comprising steps of:separately inserting either end portion of an jet pump beam disposed above an inlet mixer into a groove formed in each of a pair of projecting portions in a state that the inlet mixer is disposed between a pair of projecting portions of a transition piece provided to a riser pipe, one end portion of the inlet mixer is inserted to a diffuser provided in a reactor pressure vessel and another end portion of the inlet mixer is communicated with the riser pipe disposed in the reactor pressure vessel;arching the jet pump beam by moving a center portion of the jet pump beam upward;pushing against a second curved surface formed in a top surface of an insert member fitting into a top end portion of the inlet mixer, where the second curved surface has a second radius of curvature larger than a first radius of curvature of a first curved surface formed in a lower end portion of a screw member engaged with the arched jet pump beam, by tightening the screw member;sending ultrasonic waves to the screw member from an ultrasonic sensor while the first curved surface of the screw ...

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22-11-2012 дата публикации

Heat-Resistant Ultrasonic Sensor and Installation Method Thereof

Номер: US20120291554A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A heat-resistant ultrasonic sensor comprising:a flexible metal plate;a piezo-electric ceramics portion attached on said metal plate having a thickness of 0.5 mm or smaller and a Curie point of 200° C. or higher;an electrode member disposed on said piezo-electric ceramics portion and connected to said piezo-electric ceramics portion; andan electric insulating cover attached to said metal plate and covering said piezo-electric ceramics portion and said electrode member.2. The heat-resistant ultrasonic sensor according to claim 1 , wherein a metal wire mesh is attached to said electrode member.3. The heat-resistant ultrasonic sensor according to claim 1 , wherein said piezo-electric ceramics portion is a piezo-electric ceramics film formed on said metal plate.4. The heat-resistant ultrasonic sensor according to claim 2 , wherein said piezo-electric ceramics portion is a piezo-electric ceramics film formed on said metal plate.5. The heat-resistant ultrasonic sensor according to claim 3 , wherein said piezo-electric ceramics film is a piezo-electric ceramics film formed by the sol-gel method.6. The heat-resistant ultrasonic sensor according to claim 5 ...

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22-11-2012 дата публикации

Nuclear Power Plant and Method of Operating It

Номер: US20120294404A1
Автор:
Принадлежит: Hitachi-GE Nuclear Engergy, Ltd.

A hydrogen treatment facility for treating hydrogen without using a power source is disposed outside a reactor containment vessel and in an upper portion of a reactor building. A hydrogen detector detecting hydrogen in the reactor building is connected to a control apparatus operated by an independent power source activated at the time of a station black-out. A circulation passage for air circulation generated in the reactor building is disposed in the reactor building and outside the reactor containment vessel. A hydrogen treatment duct connects to the circulation passage and a gangway and a room with equipment. During a severe accident and station black-out and when hydrogen concentration detected by the hydrogen detection apparatus exceeds a set concentration, the hydrogen treatment duct is put in use by the control apparatus. Air containing the hydrogen is introduced into the hydrogen treatment facilities through the hydrogen treatment duct and the circulation passage. 1. A nuclear power plant comprising:a reactor pressure vessel;a reactor containment vessel for storing the reactor pressure vessel and covered with a reactor building;hydrogen treatment facilities for treating hydrogen without using a power source and disposed in the reactor building;a control apparatus operated by an independent power source activated at the time of station black-out;a hydrogen detection apparatus connected to the control apparatus;a hydrogen treatment duct put in use by the control apparatus when hydrogen concentration detected by the hydrogen detection apparatus exceeds a set concentration; anda circulation passage for generating air circulation in the reactor building by putting the hydrogen treatment duct in use, to make the circulation pass through the hydrogen treatment facilities.2. The nuclear power plant according to claim 1 ,wherein the hydrogen treatment facilities has a hydrogen treatment room disposed outside the reactor containment vessel and an upper portion of the ...

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22-11-2012 дата публикации

Nuclear Power Plant, Fuel Pool Water Cooling Facility and Method Thereof

Номер: US20120294407A1
Автор:
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A nuclear power plant comprising:a reactor pressure vessel that encompasses a reactor containing nuclear fuel;a containment vessel for housing the reactor pressure vessel;a fuel pool for storing spent fuel;a reactor building that houses the reactor pressure vessel, the containment vessel and the fuel pool;a circulating water system adapted to forced-circulating-cool the fuel pool water in the fuel pool; andat least one heat pipe for transferring heat of the fuel pool water in the fuel pool and discharging the heat to the atmosphere.2. The nuclear power plant according to claim 1 ,wherein the heat pipe has one end submerged in the fuel pool water in the fuel pool and the other end exposed to the outside of the reactor building.3. The nuclear power plant according to claim 1 , further comprisingan air duct having a passage that the other end of the heat pipe faces.4. The nuclear power plant according to claim 1 , further comprisinga fan for delivering air to a cooling part of the heat pipe.5. The nuclear power plant according to claim 1 , further comprising:a pool for storage of reactor core internal structure that is installed in the reactor building;a heat pipe for the pool for storage of reactor core internal structure, for transferring heat of pool water in the pool for storage of reactor core internal structure and discharging the heat to the atmosphere;a connecting heat pipe connecting the pool for storage of reactor core internal structure with the fuel pool.6. The nuclear power plant according to claim 1 ,wherein the heat pipe has an insert part to be inserted between a plurality of spent fuel rods in the fuel pool water in the fuel pool.7. The nuclear power plant according to claim 6 ,wherein a sectional shape of the insert part is ...

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06-12-2012 дата публикации

Wind Power Generation System and Method for Additional Installation of Wind Power Generator Therein

Номер: US20120306202A1

The present invention provides a wind power generation system capable of suppressing an increase in output variation involved in additional installation of a wind power generator without the need for a large storage battery capacity. For example, an output variation rate at a predetermined period of an existing wind power generator in an existing wind-power generating station is determined in advance, and charge/discharge control for a storage battery device is performed to reduce an output variation in a system output of the existing wind power generator so that an output variation rate of the wind-power generating system after the additional installation of the wind power generator does not exceed the determined output variation rate of the existing wind power generator. 1. A wind power generation system provided with at least one additionally installed wind power generator in a wind-power generating station having at least one existing wind power generator , comprising:at least one storage battery device;a generated power detecting device, which is configured to detect a generated output of the existing wind power generator;a charge/discharge power detecting device, which is configured to detect a charge and discharge power of the storage battery device; anda control device, which is configured to receive signals output from the generated power detecting device and the charge/discharge power detecting device, and to control a system output of the existing wind power generator, corresponding to the sum of the generated power of the existing wind power generator and the charge and discharge power of the storage battery device, by adjusting the charge and discharge of the storage battery device in such a manner that an output variation or output variation rate of the wind-power generating system at a predetermined period, during which the output variation or output variation rate is suppressed, becomes less than or equal to an estimated output variation or output ...

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20-12-2012 дата публикации

Flat battery

Номер: US20120321939A1
Принадлежит: Hitachi Maxell Energy Ltd

Provided is a flat battery with a molded gasket extending from the opening edge of the seal can to the flat portion, where the gasket may be prevented from exfoliating from the inner surface of the seal can. A flat battery ( 1 ) includes: a negative electrode can ( 10 ) (exterior can) shaped as a cylinder with a bottom; a positive electrode can ( 20 ) (seal can) having a peripheral wall ( 22 ) (cylinder portion) and a flat portion ( 21 ), the positive electrode can being disposed as an inverted dish with respect to the negative electrode can ( 10 ); and a gasket ( 30 ) molded at least on an inner surface of the positive electrode can ( 20 ), extending from the opening edge of the peripheral wall ( 22 ) to the flat portion ( 21 ). The opening edge of the sidewall of the negative electrode can ( 10 ) is fitted onto the stepped portion ( 22 c ) of the positive electrode can ( 20 ), and a portion of the gasket ( 30 ) that is located inside the opening edge portion of the peripheral wall ( 22 ) of the positive electrode can ( 20 ) with respect to the positive electrode can has a thickness smaller than that of a portion of the gasket that is located inside the stepped portion ( 22 c ) of the positive electrode can ( 20 ) with respect to the positive electrode can.

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28-02-2013 дата публикации

Initial Core of Nuclear Reactor and Method of Loading Fuel Assemblies of Nuclear Reactor

Номер: US20130051509A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. An initial core of a nuclear reactor comprising:a central region disposing a plurality of first fuel supports for supporting fuel assemblies in which a first cooling water supply passage is formed every the fuel assembly supported and introduces cooling water to the fuel assembly inserted in the first cooling water supply passage; anda peripheral region surrounding the central region, and disposing a plurality of second fuel supports for supporting fuel assemblies in which a second cooling water supply passage having a pressure loss smaller than that of the first cooling water supply passage is formed every the fuel assembly supported and introduces cooling water to the fuel assembly inserted in the second cooling water supply passage;wherein a plurality of water regions with no fuel assemblies loaded are formed right above a part of the first fuel supports in the central region;wherein the fuel assemblies disposed in the central region are supported by the remaining first fuel supports; andwherein the fuel assemblies disposed in the peripheral region are supported by the second fuel supports.2. The ...

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21-03-2013 дата публикации

Foreign Matter Inspection Device and Foreign Matter Inspection Method

Номер: US20130070084A1

Disclosed are a foreign matter inspection device and a foreign matter inspection method, in which the accurate inspection of foreign matter is performed using captured images by continuous shooting in the state in which a movement locus due to the falling caused by the movement of the foreign matter along the inner wall of a container from the horizontal direction of the container as a result of rotation is formed so as to be long. A rotating device is provided with a rotation control means for executing the rotational motion in which container holding members for holding the container in a horizontal manner or at a constant inclination angle relative to the horizontal axis of the container, and the container are rotated at an angle of 60° or more, and then stopped, wherein a foreign matter detection means detects the foreign matter according to the movement locus of the foreign matter, which is formed using the captured images obtained by the continuous shooting for each rotational motion at constant time. 1. A foreign matter inspection device , comprising:container holding members that hold cylindrical containers filled with liquid;rotating devices that rotate the containers;irradiating photographing devices that irradiate an irradiation beam to the containers and photograph foreign matter mixed in liquid in the containers; anda foreign matter detecting unit that detects the foreign matter from photographed images, whereinthe rotating device includes a rotation control unit that makes the container holding member that holds a center shaft of the container in a horizontal manner or at a constant inclination angle and the container execute a rotational motion of rotating at a rotational angle of ±60° or a range of ±60° or more and ±180° or less and then stopping,the irradiating photographing device executes photographing by continuous shooting while stopping after rotating accompanying rotation of the containers, andthe foreign matter detecting unit detects the ...

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28-03-2013 дата публикации

Nuclear Power Plant

Номер: US20130077730A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A nuclear power plant comprising:a primary containment vessel; a reactor pressure vessel installed in the primary containment vessel; a pressure suppression pool in which first cooling water is filled for reducing pressure increase in the primary containment vessel, installed in a lower portion of the primary containment vessel; and a passive pressure suppression pool cooling system,Wherein the passive pressure suppression pool cooling system has a steam condensing pool in which second 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, and;wherein another end portion of the condensed water discharge pipe is disposed in the pressure suppression pool.2. A nuclear power plant comprising:a primary containment vessel; a reactor pressure vessel installed in the primary containment vessel; and a pressure ...

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28-03-2013 дата публикации

Non-aqueous secondary battery

Номер: US20130078509A1
Автор: Eri Kojima, Jinbao Zhao
Принадлежит: Hitachi Maxell Energy Ltd

A non-aqueous secondary battery contains a positive electrode, a negative electrode, a separator and a non-aqueous electrolytic solution. The positive electrode contains a layered structure lithium-containing compound oxide, or a spinel lithium-containing compound oxide containing manganese as an active material. The non-aqueous electrolytic solution contains at least one additive selected from a sulfonic acid anhydride, a sulfonate ester derivative, a cyclic sulfate derivative and a cyclic sulfonate ester derivative, and a vinylene carbonate or a derivative of the vinylene carbonate.

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13-06-2013 дата публикации

Sliding Bearing and Pump Device Using the Same

Номер: US20130149142A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A sliding bearing comprising a substantially circular cylindrical-shaped sleeve slidingly supporting a rotatable shaft via fluid in an inner periphery thereof , hydrostatic pressure supplying passages penetrating through the sleeve and supplying high pressure fluid into the sleeve inner periphery from an external pressure source , and hydrostatic pressure pockets provided in the inner periphery of the sleeve and having radially recessed shapes , the hydrostatic pressure supplying passages being opened in the hydrostatic pressure pockets ,wherein the hydrostatic pressure pockets constitute a plurality of rows of circumferentially disposed hydrostatic pressure pockets, at least one of the hydrostatic pressure pocket rows being arranged adjacently to each of both end portions of the inner periphery of the sleeve in an axial direction of the shaft, and a circular cylindrical inner peripheral surface region in which the hydrostatic pressure pockets are not present is provided at a center portion of the sleeve so as to be interposed between ...

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11-07-2013 дата публикации

Method of Executing Water Jet Peening

Номер: US20130174627A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A method of executing water jet peening comprising:filling water in an upper cover provided with a plurality of tubular members arranged in a rectangular grid-like pattern and restrained horizontal movement by a rectangular lattice-like tube support member;moving a jet nozzle in the axial direction of the tubular member toward an inner surface of the upper cover from the tube support member through a first opening formed by the tube support member; andthen, executing water jet peening sequentially to four tubular members facing the first opening and held by the tube support member, by turning the jet nozzle ejecting a water jet.2. The method of executing water jet peening according to claim 1 , wherein the moving of the jet nozzle in the axial direction of the tubular member through the first opening is performed by moving the jet nozzle installed to a turning apparatus provided to a lifting/lowering mechanism of a nozzle lifting/lowering apparatus in the axial direction of the tubular member by the lifting/lowering mechanism; and then claim 1 , the turning of the jet nozzle is performed by the turning apparatus.3. ...

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11-07-2013 дата публикации

Ultrasonic Reactor Water Level Measuring Device and Evaluation Method

Номер: US20130174637A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. An ultrasonic reactor water level measuring device comprising:an upper tube that extends from a gas phase portion in a reactor;a lower tube that extends from a liquid phase portion in the reactor;measurement tubes that are connected to each other and arranged at multiple stages between the upper tube and the lower tube; andunits for generating and receiving ultrasonic waves and measuring levels of water within the measurement tubes, the units being arranged at bottom portions of the measurement tubes,wherein a water level within the reactor is calculated from the sum of the measured water levels, the sum excluding the height of an overlapped part of the measurement tubes.2. The ultrasonic reactor water level measuring device according to claim 1 , further comprisingseparation valves that are arranged in the middle of the upper and lower tubes,wherein when pressure on the side of the measurement tubes is equal to or lower than a set value, the separation valves are automatically closed.3. The ultrasonic reactor water level measuring device according to claim 1 ,wherein ultrasonic probes are ...

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11-07-2013 дата публикации

Reactor Water-Level/Temperature Measurement Apparatus

Номер: US20130177122A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A reactor water-level/temperature measurement apparatus for detecting a water level in a reactor on the basis of temperatures measured by making use of a plurality of thermocouples installed inside a reactor pressure vessel , the reactor water-level/temperature measurement apparatus comprising:an in-core instrumentation housing welded to the bottom of the pressure vessel;an in-core instrumentation guide tube placed between the upper portion of the in-core instrumentation housing and a reactor-core support plate;an in-core instrumentation tube inserted into the in-core instrumentation housing and the in-core instrumentation guide tube;a water-level/temperature detection sensor including one of the thermocouples and a heater wire, the thermocouples being installed at a plurality of vertical positions inside the in-core instrumentation tube;a temperature measurement device for measuring the temperatures of the thermocouples;a heater control device for controlling a current flowing to the heater wire;a storage device used for storing a threshold-value table associating a temperature indicated by the thermocouple before a current flows to the heater wire and a temperature increase indicated by the thermocouple while a current is flowing to the heater wire with a steam atmosphere, a water atmosphere and a sensor ...

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01-08-2013 дата публикации

Eddy Current Flaw Detection System and Eddy Current Flaw Detection Method

Номер: US20130193960A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. An eddy current flaw detection system comprising: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 eddy current flaw detection probe on the inspection surface;a scan control device which drives and controls the scanning device to control a scan position and an attitude angle of the eddy current flaw detection probe; andan 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 eddy current flaw detection probe, wherein said eddy current flaw detection system includes:detection point three-dimensional coordinate acquiring means which acquires three-dimensional coordinates of the detection points for each scan position of the eddy current flaw detection probe;three-dimensional flaw detection data generating means which generates three- ...

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01-08-2013 дата публикации

Preventive Maintenance Method and Apparatus for a Structural Components in a Reactor Pressure Vessel

Номер: US20130195236A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD

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. 1. A water jet peening method comprising the steps of:preparing a water jet peening apparatus having a supporting member, a first divider plate mounted on one end of the supporting member, a nozzle support body formed by disposing a jet nozzle around the supporting member, and a second divider plate mounted on the supporting member, the jet nozzle being disposed between the first divider plate and the 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 the 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; andsubjecting 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.2. The water jet peening method according to claim 1 , further comprising the steps of:before filling the water into the internal area ...

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01-08-2013 дата публикации

Method of Repairing Shroud Support and Repair Apparatus Thereof

Номер: US20130195238A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A method of repairing a shroud support comprising the steps of:setting a plurality of rails along a weld of said shroud support in a reactor pressure vessel over either an entire perimeter on an inner circumference of said reactor pressure vessel or a repair range;attaching movably a repair device to said rail; andperforming repair operation of said weld of said shroud support by said repair device.2. The method of repairing a shroud support according to claim 1 , comprising step of:setting a first support apparatus on each upper end of a part of a plurality of control rod drive mechanism housings installed to a bottom of said reactor pressure vessel;wherein said setting of said rails is performed by setting on an support arm attached to each support apparatus.3. The method of repairing a shroud support according to claim 2 , wherein said setting of said rails comprises steps of:setting a support base on each upper end of said part of said plurality of control rod drive mechanism housings;performing said set of said first support apparatus by setting said first support apparatus on said support base;positioning horizontally a ...

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08-08-2013 дата публикации

Suppression Method for Corrosion of Carbon Steel Member

Номер: US20130202791A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A suppression method for corrosion of a carbon steel member , comprising steps of:connecting a pipe having a pump to a piping including the carbon steel member composing a plant;forming a nickel metal film on an inner surface of the piping by supplying a first film forming liquid containing nickel ions, whose pH is adjusted to a value in a range between 4.0 and 9.0, into the piping through the pipe;forming a nickel ferrite film on a surface of the nickel metal film formed on the inner surface of the piping by supplying a second film forming liquid including a first agent containing iron (II) ions, a second agent containing nickel ions, and a third agent for oxidizing the iron (II) ions, whose pH is adjusted by addition of a pH adjustment agent to a value within a range of more than 5.5 to 9.0 or less, into the piping through the pipe;removing the pipe from the piping after the formation of the nickel ferrite film; andafter the formation of the nickel ferrite film, transforming the nickel metal film into a nickel ferrite film,wherein the steps of connecting the pipe, forming the nickel metal film, forming the nickel ferrite film, and removing the ...

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29-08-2013 дата публикации

Nuclear Power Plant

Номер: US20130223581A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A nuclear power plant comprising:a first reactor containment vessel internally having a dry well and a pressure suppression chamber mutually isolated, said pressure suppression chamber forming a suppression pool being filled with cooling water;a reactor pressure vessel disposed in said dry well in said first reactor containment vessel;a second reactor containment vessel surrounding said first reactor containment vessel and forming a cooling water pool being filled with cooling water at a bottom, said cooling water pool in said second reactor containment vessel adjoining said suppression pool with said first reactor containment vessel intervening between these pools;a steam discharge apparatus; anda reactor cooling apparatus,wherein said steam discharge apparatus has a steam discharge pipe connected to said reactor pressure vessel and immersed in said cooling water in said suppression pool, and a first open/close valve installed in said steam discharge pipe; andthe reactor cooling apparatus has an evaporator installed in said reactor pressure vessel for evaporating a cooling medium, a condenser disposed above said cooling water pool between said ...

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06-02-2014 дата публикации

Method of Depositing Noble Metal on Structure Member of Nuclear Plant

Номер: US20140037037A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A method of depositing a noble metal on a structure member of a nuclear plant , comprising:a step of executing reduction decontamination of a surface of said structure member of said nuclear plant in contact with reactor water by using an aqueous solution of a reduction decontamination agent; anda step of bringing said aqueous solution including noble metal ions and reduction agent generated by injecting chemical including said noble metal ions, and said reduction agent into said aqueous solution of said reduction decontamination agent into contact with said surface of said structure member on which said reduction decontamination is executed and depositing said noble metal on said surface, during at least one period among a first period that said reduction decontamination agent remains in said aqueous solution after a part of said reduction decontamination agent is decomposed in said decomposition process of said reduction decontamination agent to be executed after said reduction decontamination and a second period that purification of ...

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06-02-2014 дата публикации

Fuel Assembly and Reactor Core

Номер: US20140037039A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. 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; andthe 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.2. A fuel assembly according to claim 1 , wherein:the plurality of fuel rods further includes third layer ...

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06-03-2014 дата публикации

GAS TREATMENT EQUIPMENT OF NUCLEAR POWER PLANT

Номер: US20140064427A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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 . The steam is condensed in the heat exchanger tubes and generates mists. The mists are removed by a mist separator together with the radioactive nuclides. The gas including hydrogen fed from the mist separator in the casing is heated by the aforementioned steam and is introduced into the catalytic layer. Hydrogen is combined with oxygen in the catalytic layer to steam. 1. A gas treatment equipment of a nuclear power plant comprising:a gas treatment apparatus for treating gas components included in gas supplied from a primary containment vessel; and a mist separator,wherein said gas treatment apparatus includes a casing and a gas component treatment member installed in said casing for treating said gas components;wherein a heating device for heating said gas in said casing supplied to said gas component treatment member by heat held by said gas, which includes said steam and gas components, supplied from a primary containment vessel is installed in said casing;wherein said mist separator for removing mists generated by condensation of said steam in said heating device together with a part of said gas components adsorbed to said mists is connected to said heating device; andwherein a pipe path for introducing said gas including said gas components not removed by said mist separator from said mist separator into said casing is installed.2. The gas treatment equipment of a nuclear power plant according to claim 1 , wherein said heating device is disposed on ...

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06-03-2014 дата публикации

Fuel Assembly and Core of Nuclear Reactor

Номер: US20140064433A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

In a fuel assembly having fuel rods U to U, and P not containing gadolinia, and fuel rods G-G containing gadolinia, the concentrations a of gadolinia in nuclear fuel materials A (8 wt % and 10 wt %) satisfy 0.7 Подробнее

13-03-2014 дата публикации

Electrochemical Corrosion Potential Sensor

Номер: US20140069810A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. An electrochemical corrosion potential sensor comprising:a sensor unit including a tube-shaped metal casing and a corrosion potential detecting electrode attached to the metal casing and electrically insulated from the metal casing;a lead wire connected to the corrosion potential detecting electrode, passed through in the sensor unit and extended to an outside of the sensor unit; anda quasi-reference electrode disposed in the metal casing of the sensor unit and made of a less noble metal electrically connected with either the corrosion potential detecting electrode or the metal casing, the less noble metal generating potential less noble than the corrosion potential detecting electrode, the lead wire and the metal casing.2. The electrochemical corrosion potential sensor according to claim 1 , wherein the sensor unit includes a tube-shaped insulator joining between the corrosion potential detecting electrode and the metal casing;wherein the lead wire passes through the insulator and metal casing; andwherein the quasi-reference electrode is connected to the lead wire in the metal casing.3. The electrochemical corrosion potential sensor according to claim 2 , wherein the corrosion potential detecting electrode is a Pt electrode.4. The electrochemical corrosion potential sensor according to claim 1 , wherein the sensor unit includes an insulator in which a sealed region is formed attached to the metal casing;wherein the corrosion potential detecting ...

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05-01-2017 дата публикации

Benzothiadiazole-based conjugated molecules capable of forming films on conductive surfaces by electrochemical method

Номер: US20170002024A1

The present disclosure provides new materials that combine the advantages of well-defined polymeric starting materials and the convenience of surface modification by physical methods into one package and, thus, offers a general and powerful platform suitable for use in numerous applications.

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24-04-2014 дата публикации

Passive Residual Heat Removal System and Nuclear Power Plant Equipment

Номер: US20140112426A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A passive residual heat removal system , comprising:a primary containment vessel including a drywell to surround a reactor pressure vessel, and a suppression chamber internally provided with a suppression pool;a vent line connecting the drywell and the suppression pool, the vent line being fitted with a plurality of openings in the suppression pool;a coolant pool filled with a coolant and provided above the primary containment vessel;a heat exchanger placed under the coolant in the coolant pool;a steam suction line connecting the drywell and the heat exchanger;a condensate storage tank disposed below the heat exchanger and above an upper end of a reactor core placed in the reactor pressure vessel;a first condensate discharge line connecting the condensate storage tank and the heat changer;a non-condensate gas discharge line connected at a first end thereof to an upper section of the condensate storage tank and at a second end thereof to the suppression pool, the second end of the non-condensate gas discharge line being open at a position higher than a highest opening of the vent line in the suppression pool;a ...

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22-05-2014 дата публикации

Platinum Oxide Colloidal Solution, Manufacturing Method Therefor, Manufacture Apparatus Thereof, and Method of Injection Noble Metal of Boiling Water Nuclear Power Plant

Номер: US20140140465A1
Принадлежит: Hitachi-GE Nuclear Energy Ltd.

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. 1. A method of manufacturing a platinum oxide colloidal solution comprising an ion exchange process of substituting hydrogen ions for cations included in an aqueous solution of hexahydroxoplatinate salt and generating a suspension; anda colloid generation process of irradiating gamma rays to said suspension.2. The method of manufacturing a platinum oxide colloidal solution according to claim 1 , wherein said aqueous solution comes into contact with a hydrogen form cation exchange resin in said ion exchange process.3. The method of manufacturing a platinum oxide colloidal solution according to claim 1 , wherein said hexahydroxoplatinate salt is sodium hexahydroxoplatinate or potassium hexahydroxoplatinate.4. The method of manufacturing a platinum oxide colloidal solution according to claim 1 , wherein said aqueous solution includes alcohol.5. The method of manufacturing a platinum oxide colloidal solution according to claim 4 , wherein when the number of carbons configuring a molecule of said alcohol is n claim 4 , a concentration of said alcohol is lower than 0.17/n (mM).6. The method of manufacturing a ...

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02-04-2015 дата публикации

IMAGING DEVICE

Номер: US20150092085A1

An imaging device includes an imaging unit, a signal processing unit, a frequency dividing unit, a noise processing unit, a noise frequency unifying unit, an edge processing unit, an edge frequency unifying unit, a synthesizing unit, and a control unit. The control unit controls the rates of the noise processing results of respective frequency components unified by the noise frequency unifying unit, and the rates of the edge processing results of the respective frequency components unified by the edge frequency unifying unit in accordance with control of operations of constituent elements included in the imaging device. 1. An imaging device outputting a signal corresponding to an object and obtained by imaging the object , comprising:an imaging unit imaging the object and generating an electric signal corresponding to the imaged object;a signal processing unit processing the electric signal generated by the imaging unit to generate a video signal;a frequency dividing unit dividing the video signal generated by the signal processing unit into a plurality of frequency components;a noise processing unit performing noise processing for each of the frequency components divided by the frequency dividing unit to output noise processing results;a noise frequency unifying unit unifying the results output from the noise processing unit;an edge processing unit performing edge processing for each of the frequency components divided by the frequency dividing unit to output edge processing results;an edge frequency unifying unit unifying the results output from the edge processing unit;a synthesizing unit synthesizing the results output from the noise frequency unifying unit and the results output from the edge frequency unifying unit; anda control unit controlling operations of constituent elements included in the imaging device,wherein the control unit controls the rates of the noise processing results of the respective frequency components unified by the noise frequency ...

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31-03-2022 дата публикации

CHEMICAL DECONTAMINATION METHOD

Номер: US20220102019A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

A chemical decontamination method capable of improving the decontamination efficiency of chemical decontamination of a steam dryer in the RPV is provided. In particular, the decontamination method includes feeding a chemical decontamination aqueous solution into a reactor pressure vessel in which a steam dryer is arranged, and after chemical decontamination of the steam dryer, the water level of the chemical decontamination aqueous solution existing in the reactor pressure vessel is lowered to a first water level below the lower end of the steam dryer. 1. A chemical decontamination method comprising:feeding a chemical decontamination aqueous solution into a reactor pressure vessel in which a steam dryer is arranged, andafter chemical decontamination of the steam dryer, a water level of the chemical decontamination aqueous solution existing in the reactor pressure vessel is lowered to a first water level below a lower end of the steam dryer.2. The chemical decontamination method according to claim 1 , whereinthe chemical decontamination of the steam dryer is performed by raising the water level of the chemical decontamination aqueous solution in the reactor pressure vessel to a second water level above an upper end of the steam dryer, andthen the water level of the chemical decontamination aqueous solution is lowered from the second water level to the first water level.3. The chemical decontamination method according to claim 2 , whereinthe first water level is a water level in a range below the lower end of the steam dryer and above a shroud head attached to an upper end of a cylindrical reactor core shroud arranged in the reactor pressure vessel.4. The chemical decontamination method according to claim 2 , whereinthe second water level is located above the upper end of the steam dryer, and is a water level within a range at or below a position of a lower surface of a pressing member that is attached to an upper lid that seals the reactor pressure vessel and presses ...

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26-06-2014 дата публикации

Radionuclide Adsorbent, Method of Producing Radionuclide Adsorbent and Production Apparatus Thereof

Номер: US20140178282A1
Автор: Asano Takashi, KANI Yuko
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A method of producing a radionuclide adsorbent , the steps of:storing a silicotitanate compound in a caustic treatment apparatus, andbring said silicotitanate compound into contact with a sodium hydroxide solution having a sodium hydroxide concentration within a range of 0.5 Mol/L or more but less than 2.0 Mol/L in said caustic treatment apparatus.2. The method of producing a radionuclide adsorbent according to claim 1 , wherein said sodium hydroxide concentration of said sodium hydroxide solution in contact with said silicotitanate compound is within a range from 0.8 Mol/L to 1.5 Mol/L.3. The method of producing a radionuclide adsorbent according to claim 1 , wherein said silicotitanate compound is immersed in said sodium hydroxide solution in said caustic treatment apparatus for 0.5 hour to 2 hours.4. The method of producing a radionuclide adsorbent according to claim 2 , wherein said silicotitanate compound is immersed in said sodium hydroxide solution in said caustic treatment apparatus for 0.5 hour to 2 hours.5. The ...

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31-07-2014 дата публикации

Inspection Apparatus and Method for Producing Image for Inspection

Номер: US20140210988A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. An inspection apparatus comprising:an image pick-up unit provided with an optical video camera;an image obtaining unit which fetches a video image that contains a signal (noise) that is substantially independent of each frame of the video image obtained by picking up a video image of an inspection object by the image pick-up unit;a local alignment unit which locally aligns a plurality of frames of the video image with different time phases;a frame synthesizing unit which synthesizes the plurality of frames of the video image aligned by the local alignment unit for generating an image formed of the synthesized frames with an SN ratio higher than the SN ratio of each of the frames before frame synthesis; andan image output unit for displaying or recording an image formed of the synthesis frame generated by the frame synthesizing unit,a noise amount measurement unit which measures an amount of the signal (noise) substantially independent of the respective frames of the video image fetched from the optical video camera of the image pick-up unit in the image obtaining unit; anda processing parameter change unit ...

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14-08-2014 дата публикации

Higher-Order Vibration Control Device

Номер: US20140229020A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

Higher-order vibration is controlled in an event that an impact load such as an aircraft impact is applied to a nuclear plant. 1. A higher-order vibration control device comprising:a housing secured to a large-scale construction;an impactor housed movably in the housing; anda locking mechanism capable of selectively switching between release and restraint of movement of the impactor in the housing.2. The higher-order vibration control device according to claim 1 , whereinthe locking mechanism releases movement of the impactor in an event that a flying object may possibly impact the large-scale construction.3. The higher-order vibration control device according to claim 1 , whereinthe locking mechanism restrains movement of the impactor in case of the occurrence of an earthquake or releases movement of the impactor in other cases.4. The higher-order vibration control device according to claim 1 , whereinthe impactor is a pendulum capable of swinging in the housing.5. The higher-order vibration control device according to claim 4 , whereinthe locking mechanism releases movement of the impactor in an event that a flying object may possibly impact the large-scale construction.6. The higher-order vibration control device according to claim 4 , whereinthe locking mechanism restrains movement of the impactor in case of an occurrence of an earthquake and releases movement of the impactor in other cases.7. The higher-order vibration control device according to claim 2 , whereinthe locking mechanism includes a hydraulic pump; a pair of pipes through which hydraulic oil supplied from the hydraulic pump flows; a cylinder connected to the pipes; a piston which slides in the cylinder; a cylinder rod attached to the piston; and a reaction plate which is attached to the cylinder rod and moves back and forth against the impactor.8. The higher-order vibration control device according to claim 2 , whereinthe locking mechanism includes a shaft; a reaction plate which is attached to the ...

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21-08-2014 дата публикации

Water Jet Peening Apparatus and Water Jet Peening Method

Номер: US20140233689A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A water jet peening apparatus comprising:a casing; a high-pressure under-water pump installed on said casing; an injection nozzle to which water pressurized by said high-pressure under-water pump is supplied; and an injection nozzle moving apparatus installed in said casing for moving said injection nozzle.2. The water jet peening apparatus according to claim 1 , wherein a high-pressure hose connected to said high-pressure under-water pump and said injection nozzle is disposed in said casing.3. The water jet peening apparatus according to claim 1 , wherein said high-pressure under-water pump is installed on an upper end of said casing.4. The water jet peening apparatus according to claim 2 , wherein said high-pressure under-water pump is installed on an upper end of said casing.5. A water jet peening method comprising the steps of:disposing a water jet peening apparatus having a casing, a high-pressure under-water pump installed on said casing, an injection nozzle to which water pressurized by said high-pressure under-water pump is supplied, and an injection nozzle moving apparatus installed in said casing for moving ...

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06-08-2015 дата публикации

MONITORING SYSTEM AND SLAVE DEVICE FOR PHOTOVOLTAIC POWER GENERATION PLANT

Номер: US20150222227A1

A monitoring system includes a slave device () and a master device (). The slave device () superposes a current signal, which represents measurement data obtained by measuring each of one or more solar cell panels included in plural solar cell panels (P to P) constituting a solar cell string (), to a DC current path. The DC current path includes plural power lines (L to L), a first trunk power line (), and a second trunk power line (). The master device () is connected onto the first trunk power line (), second trunk power line (), or both of the trunk power lines, and receives the measurement data from the slave device (). Accordingly, the communication performance between the slave device and master device in, for example, a monitoring system that performs monitoring in units of a solar cell panel can be improved. 1. A slave device employed in a monitoring system for photovoltaic power generation plant , the photovoltaic power generation plant comprising:a first solar cell string having a plurality of first solar cell panels connected in series with one another over a plurality of first power lines;a first trunk power line coupled to a solar cell panel on the highest voltage side out of the plurality of first solar cell panels;a second trunk power line coupled to a solar cell panel on the lowest voltage side out of the plurality of first solar cell panels; andan inverter that acquires DC power, which is produced by the first solar cell string, over a first DC current path including the plurality of first power lines, the first trunk power line, and the second trunk power line, and converts the DC power into AC power, whereinthe slave device includes a transmitter that superposes a first current signal, which represents first measurement data, to the first DC current path to transmit the first measurement data obtained by measuring each of one or more solar cell panels included in the plurality of first solar cell panels, to a remotely disposed master device.2. The ...

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06-08-2015 дата публикации

IMAGING APPARATUS

Номер: US20150222829A1

An imaging apparatus includes an imaging unit that outputs an optical image received by an optical unit as an electric signal, according to set imaging parameters; a shading correcting unit that outputs an electric signal obtained by performing shading correction according to the imaging parameters on the electric signal output by the imaging unit; an output unit that outputs the electric signal output from the shading correcting unit; a detecting unit that detects the electric signal output from the shading correcting unit and output brightness information; and a control unit that sets the imaging parameters of the imaging unit and strength of the shading correction by the shading correcting unit, on the basis of the brightness information output by the detecting unit. 1. An imaging apparatus comprising:an imaging unit that outputs an optical image received by an optical unit as an electric signal, according to set imaging parameters;a shading correcting unit that outputs an electric signal obtained by performing shading correction according to the imaging parameters on the electric signal output by the imaging unit;an output unit that outputs the electric signal output from the shading correcting unit;a detecting unit that detects the electric signal output from the shading correcting unit and output brightness information; anda control unit that sets the imaging parameters of the imaging unit and strength of the shading correction by the shading correcting unit, on the basis of the brightness information output by the detecting unit.2. The imaging apparatus according to claim 1 , wherein the imaging parameters of the imaging unit include a parameter to control gain or a diaphragm.3. The imaging apparatus according to claim 2 , wherein the shading correcting unit has correction tables in which correction data according to screen position information corresponding to a plurality of diaphragms is stored and the shading correcting unit complements correction data ...

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13-08-2015 дата публикации

CORE OF LIGHT WATER REACTOR AND FUEL ASSEMBLY

Номер: US20150228362A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. A core of a light water reactor , comprising:a plurality of fuel assemblies including a plurality of isotopes of transuranic nuclides,wherein said transuranic nuclides included in said plurality of fuel assemblies are different in a recycle frequency, and among said fuel assemblies, a plurality of fuel assemblies including said transuranic nuclides having a smallest recycle frequency are disposed at a central part of said core, and between said central part and an outermost layer zone of said core, said fuel assemblies including said transuranic nuclides having larger recycle frequencies are disposed on a side of said outermost layer zone of said core.2. The core of a light water reactor according to claim 1 ,wherein said fuel assemblies having a nuclear fuel material including the highest rate of Pu-239 in said TRU are disposed at said central part of said core, and between said central part and said outermost layer zone of said core, the fuel assemblies having a nuclear fuel material including a lower rate of Pu-239 in said TRU is disposed on said side of said outermost layer zone of said core. This application is a continuation of U.S. patent application Ser. No. 12/978,198, filed on ...

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27-08-2015 дата публикации

IMAGE SIGNAL PROCESSING APPARATUS, IMAGE SIGNAL PROCESSING METHOD, AND IMAGE CAPTURING APPARATUS

Номер: US20150243002A1

An image signal processing apparatus includes an image signal input unit; a gradation decrease evaluation device that evaluates a decrease in gradation within a certain area in image signals; a gradation loss evaluation device that evaluates a degree of gradation loss within a certain area in image signals; an image signal correction device that performs signal level correction processing on image signals and outputs the processing result; and an image signal correction control device that controls strength of correction by the image signal correction unit, using both the gradation decrease evaluated value which is output by the gradation decrease evaluation device and the gradation loss evaluated value which is output by the gradation loss evaluation unit. 1. An image signal processing apparatus comprising:an image signal input device to which image signals are input;a gradation decrease evaluation device that calculates a gradation decrease evaluated value for evaluating a degree of gradation decrease with respect to an object which is included in the image signals from the image signal input unit;a gradation loss evaluation device that calculates a gradation loss evaluated value for evaluating a degree of gradation loss with respect to an object which is included in the image signals;an image signal correction device that performs signal level correction processing on the input image signals and outputs image signals whose signal levels have been corrected; andan image signal correction control device that controls correction strength of image signal correction processing that is executed by the image signal correction unit, using both the gradation decrease evaluated value which is output by the gradation decrease evaluation device and the gradation loss evaluated value which is output by the gradation loss evaluation unit,wherein the image signal correction control device performs control to decrease the correction strength, if having determined that the ...

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13-11-2014 дата публикации

Ultrasonic Measurement System

Номер: US20140331771A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. An ultrasonic measurement system comprising:an ultrasonic transducer with a piezoelectric element;a high-temperature MI cable having a built-in strand connected to the ultrasonic transducer, the cable including a metallic sheath;a temperature sensor contained in the high-temperature MI cable;an ultrasonic transmitter/receiver that makes the ultrasonic transducer to transmit ultrasonic waves and to receive the waves reflected from an object whose thickness is to be measured;a temperature-measuring instrument using the temperature sensor to measure temperature of the object whose thickness is to be measured; anda signal logger configured to compensate for a change in a sound speed of an ultrasonic wave propagating through the object whose thickness is to be measured, by use of information on the temperature measured by the temperature-measuring instrument, and then measure the thickness of the object.2. The ultrasonic measurement system according to claim 1 , wherein:the high-temperature MI cable has a first strand and a second strand,the first strand and the second strand are joined together at one end of each strand to constitute a thermocouple section,ultrasonic measurements are conducted via the first strand and the metallic sheath, anda protecting circuit is provided to cut off an ultrasonic-wave measuring signal and allow only an electromotive force generated by the thermocouple section, to pass through the circuit.3. The ultrasonic measurement system according to claim 1 , wherein:the high-temperature MI cable has a first strand and a second strand,the first strand and the second strand are joined together at one end of each strand to ...

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04-12-2014 дата публикации

Ultrasonic Observation Equipment, Ultrasonic Observation System, and Ultrasonic Observation Method

Номер: US20140355378A1
Принадлежит: HITACHI-GE NUCLEAR ENERGY, LTD.

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. 1. Ultrasonic observation equipment comprising:a single element ultrasonic sensor including a single transducer element and configured to transmit an ultrasonic wave on a basis of a pulse wave;an ultrasonic array sensor including a plurality of transducer elements and configured to receive an ultrasonic reflected wave;a pulsar configured to supply the pulse wave to the single element ultrasonic sensor;a receiver configured to receive an electric signal from the transducer elements included in the ultrasonic array sensor;an amplification and conversion unit configured to amplify the electric signal of each of the transducer elements included in the ultrasonic array sensor received by the receiver, convert the electric signal into a digital signal, and arrange the digital signal in a serial order so as to generate a serial digital signal; andan image generator configured to generate an image on a basis of the serial digital signal.2. The ultrasonic observation equipment according to claim 1 ,wherein the single element ultrasonic sensor and the ultrasonic array sensor are arranged in such a manner that a center of the single element ultrasonic sensor matches a center of the ...

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28-09-2017 дата публикации

FOCUS CONTROL DEVICE, IMAGING DEVICE, AND FOCUS CONTROL METHOD

Номер: US20170276902A1

In order to perform an autofocus operation, a controller of a focus control device selects subject information relating to the current magnification from subject information including previous focus states stored in a storage unit in advance, and determines a focus lens driving range on the basis of a focal length associated with the selected subject information. After the focus lens driving range is determined, a contrast-based autofocus operation is performed within that driving range. Therefore, it is possible to reduce the time taken to obtain the focus state and improve reliability of the focusing. 1. A focus control device comprising:a driving unit configured to drive a focus lens;a storage unit configured to store subject information obtained through a focus lens and a zoom lens; anda controller configured to obtain a focus lens driving range on the basis of the subject information including previous focus states stored in the storage unit and scan a focus state by minimizing the focus lens driving range to perform an autofocus operation.2. The focus control device according to claim 1 , wherein the controller obtains a position and a magnification of the lens and performs computation using a magnification and a focal length of the subject information including previous focus states stored in the storage unit to obtain the focus lens driving range from a value of the subject information corresponding to an approximate magnification.3. The focus control device according to claim 1 , wherein the controller determines whether or not an autofocus operation is performed by expanding the driving range if it is difficult to obtain a focus state within the focus lens driving range.4. The focus control device according to claim 2 , wherein the controller obtains a contrast signal amplitude (contrast signal level) and a ratio between the contrast signal level and a focus lens shift amount (contrast change rate) from a contrast signal obtained by driving the focus lens ...

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08-07-1986 дата публикации

多層配線を有する電子装置

Номер: JPS61150237A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
17-01-1989 дата публикации

Compound type laser length measuring system and length measuring apparatus

Номер: JPS6412203A
Принадлежит: Hitachi Electronics Engineering Co Ltd

Подробнее
03-04-1987 дата публикации

潤滑油監視装置

Номер: JPS6272998A
Принадлежит: Hitachi Seiki Co Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
06-03-1987 дата публикации

スキヤナ

Номер: JPS6251368A
Принадлежит: Hitachi Electronics Engineering Co Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
22-03-1989 дата публикации

Lead frame

Номер: JPS6476745A

Подробнее
02-02-1985 дата публикации

半導体集積回路装置

Номер: JPS6021557A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
14-03-1986 дата публикации

半導体集積回路装置

Номер: JPS6151958A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
03-03-1986 дата публикации

光電子装置

Номер: JPS6143490A
Принадлежит: HITACHI LTD, Hitachi Tohbu Semiconductor Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
30-03-1988 дата публикации

紙幣厚み検出装置

Номер: JPS6370106A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
24-04-1986 дата публикации

増幅回路

Номер: JPS6180906A
Принадлежит: HITACHI LTD, Hitachi Tohbu Semiconductor Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
10-03-1989 дата публикации

Data discriminating circuit

Номер: JPS6464413A

Подробнее
01-02-1986 дата публикации

偏向ヨ−クの検査装置

Номер: JPS6124124A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
12-01-1988 дата публикации

タスクスケジユ−ル方式

Номер: JPS636655A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
26-12-1988 дата публикации

ディスク装置

Номер: JPS63317982A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
16-05-1986 дата публикации

産業用ロボツトの座標変換方式

Номер: JPS6198404A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
22-12-1982 дата публикации

Wiper driving system

Номер: JPS57209443A
Автор: Kazuo Nobe

Подробнее
24-09-1985 дата публикации

半導体集積回路装置

Номер: JPS60187055A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
10-10-2012 дата публикации

Method for producing lithium ion secondary battery

Номер: JP5046352B2
Принадлежит: Hitachi Maxell Energy Ltd

Подробнее
16-08-1978 дата публикации

Electric hot-air heater

Номер: JPS5393648A
Автор: Noboru So

Подробнее
06-03-1984 дата публикации

半導体装置の製造方法

Номер: JPS5940542A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
26-01-1979 дата публикации

Enclosing process of sheathed heater

Номер: JPS5410442A
Автор: Katsuhiro Yamazaki

Подробнее
02-02-1999 дата публикации

テクスチャ加工装置

Номер: JPH1128591A
Принадлежит: Hitachi Electronics Engineering Co Ltd

(57)【要約】 【目的】 ガラス製等のディスク表面にレーザを用いた テクスチャ加工を行う際に、このディスク表面に形成さ れるバンプ径を所望に調整できるようにする。 【構成】 CO 2 レーザからなるレーザ光源1からのレ ーザビームはパルス化されると共にガラス製のディスク 2に対してバンプを形成するのに最適なパワーとなるよ うに調整された上で、入射面20aが平面で、出射面2 0bが円錐面となった第1のコーンレンズ20と、第2 のコーンレンズ21は入射面21aが円錐面で、出射面 21bが平面となった第2のコーンレンズ21はとから なる輪帯開口ビームエキスパンダ6により所定の外径及 び内径に拡大した円環状ビームに変換し、かつ平行光束 化させた上で、対物光学系7によりディスク2の所定の 位置に照射される。

Подробнее
28-01-2015 дата публикации

Non-aqueous secondary battery

Номер: JP5658821B2
Принадлежит: Hitachi Maxell Energy Ltd

Подробнее
18-04-1986 дата публикации

信号処理回路

Номер: JPS6175672A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
22-01-1986 дата публикации

半導体装置

Номер: JPS6113709A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
11-05-1984 дата публикации

Dma制御装置アドレス空間の拡張方法

Номер: JPS5981724A
Принадлежит: Hitachi Electronics Engineering Co Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

Подробнее
15-05-1987 дата публикации

ガラス基板表面検査装置受光系

Номер: JPS62105038A
Принадлежит: Hitachi Electronics Engineering Co Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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Patent JPS6260069B2

Номер: JPS6260069B2

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知識の自動収集方式

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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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Package inspection equipment

Номер: JPS6466546A
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電流電圧変換回路

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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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情報処理装置

Номер: JPS60129839A

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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Electric hot-air heater

Номер: JPS5393650A
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Oil-based pigment ink composition for inkjet printer

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Sample-and-hold circuit for high speed waveform

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Device to prevent tool from slipping out of its holder

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Method of controlling thickness of film

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電気化学素子の製造方法

Номер: JP2012195296A
Принадлежит: Hitachi Maxell Energy Ltd

【課題】生産性に優れた電気化学素子の製造方法を提供する。 【解決手段】本発明の電気化学素子の製造方法は、正極、負極およびセパレータを含む渦巻状の電極体を備える電気化学素子の製造方法であって、前記セパレータは、熱可塑性樹脂を主体として含む第1多孔質層と、耐熱温度が150℃以上の絶縁性粒子を主体として含む第2多孔質層とを備え、前記セパレータは、両面の摩擦係数が異なっており、前記セパレータの摩擦係数の低い面側を巻回軸側に配置して、前記セパレータを前記巻回軸に巻き付ける工程と、前記セパレータと共に前記正極および前記負極を巻回する工程とを含むことを特徴とする。 【選択図】図1

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Pll周波数シンセサイザ用半導体集積回路装置

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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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インタ−フエイス回路

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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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紙葉類の整理装置

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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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Flame detecting device

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半導体装置およびその製造方法並びにそれに使用されるリードフレーム

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Принадлежит: HITACHI LTD, Hitachi Tohbu Semiconductor Ltd

(57)【要約】 【課題】 ZIP・ICの蟹足を防止する。 【解決手段】 ZIP・IC32の製造方法において、 アウタリード20L、20S群に複数段のタイバーを互 いに平行に架設しておき、アウタリード20L、20S の屈曲成形に際し、各タイバーを隣合うアウタリード間 で切断し、各タイバー切断痕15A、16A、17Aに て屈曲させる。アウタリード20L、20Sは両脇のタ イバーを対称形に均等に切断されるため、アウタリード のタイバーの両脇の切断痕15A、16A、17Aは対 称形に形成された状態になる。アウタリードがタイバー 切断痕15A、16A、17Aにて屈曲されると、アウ タリードはそれ自体の中心線に沿って適正に屈曲された 状態になる。その結果、アウタリード群が蟹足状態に成 形されるのを防止できる。 【効果】 蟹足の防止でZIP・ICをプリント配線基 板に適正に実装できる。

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洗浄槽の温度制御方式

Номер: JPS6314433A
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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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印刷装置

Номер: JPS6223756A
Принадлежит: Hitachi Electronics Engineering Co Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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重ね送り検出装置

Номер: JPS6382260A
Принадлежит: Hitachi Electronics Engineering Co Ltd

(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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デ−タベ−ス・システムにおけるデ−タ処理方式

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(57)【要約】本公報は電子出願前の出願データであるた め要約のデータは記録されません。

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Chuck

Номер: JPS54145078A
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