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Inspection Apparatus and Method for Producing Image for Inspection

Номер патента: US20120026317A1. Автор: . Владелец: HITACHI-GE NUCLEAR ENERGY, LTD.. Дата публикации: 02-02-2012.
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 ...

WELDED PORTION INSPECTION APPARATUS OF REACTOR PRESSURE VESSEL

Номер патента: US20120051483A1. Автор: Kobayashi Ryosuke, KOMURO Hidetaka, Okada Satoshi, OTANI Kenichi, TAKATORI Yosuke. Владелец: HITACHI-GE NUCLEAR ENERGY, LTD.. Дата публикации: 01-03-2012.
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 ...

FAST BREEDER REACTOR TYPE NUCLEAR POWER PLANT SYSTEM

Номер патента: US20120140866A1. Автор: Fujimata Kazuhiro, Fujimura Koji, Itooka Satoshi, Namba Koji. Владелец: HITACHI-GE NUCLEAR ENERGY, LTD.. Дата публикации: 07-06-2012.
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 ...

Method of Checking Installed State of Jet Pump Beam

Номер патента: US20120281800A1. Автор: . Владелец: HITACHI-GE NUCLEAR ENERGY, LTD.. Дата публикации: 08-11-2012.
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 ...

Heat-Resistant Ultrasonic Sensor and Installation Method Thereof

Номер патента: US20120291554A1. Автор: BABA Atsushi, KOIKE Masahiro, MUSHA Yoshinori. Владелец: HITACHI-GE NUCLEAR ENERGY, LTD.. Дата публикации: 22-11-2012.
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 ...

Nuclear Power Plant and Method of Operating It

Номер патента: US20120294404A1. Автор: . Владелец: Hitachi-GE Nuclear Engergy, Ltd.. Дата публикации: 22-11-2012.
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 ...

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

Номер патента: US20120294407A1. Автор: . Владелец: HITACHI-GE NUCLEAR ENERGY, LTD.. Дата публикации: 22-11-2012.
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 ...

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

Номер патента: US20120306202A1. Автор: HOSHINO Naoki, Setoguchi Satoshi, Takahashi Masaya. Владелец: Hitachi Engineering & Services Co., Ltd.. Дата публикации: 06-12-2012.
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 ...

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

Номер патента: US20130051509A1. Автор: AOYAMA Motoo, Ishii Kazuya, MITSUYASU Takeshi, Nakadozono Naoyuki. Владелец: HITACHI-GE NUCLEAR ENERGY, LTD.. Дата публикации: 28-02-2013.
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 ...

Foreign Matter Inspection Device and Foreign Matter Inspection Method

Номер патента: US20130070084A1. Автор: Asano Kunitaka, Fukuda Hirohisa, Katane Tadahiro, Yamazaki Hiromi. Владелец: Hitachi Information & Control Solutions, Ltd.. Дата публикации: 21-03-2013.
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 ...