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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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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 2459. Отображено 198.
27-07-2001 дата публикации

СПОСОБ КОНТРОЛЯ ЭКСПЛУАТАЦИОННОЙ ГОТОВНОСТИ АРМАТУРЫ

Номер: RU2171462C2

Способ может применяться для контроля неисправности трубопроводной арматуры. Определяют по меньшей мере одно измеренное значение для специфичной для арматуры величины и сравнивают с ранее установленным значением. Предусмотрено, что измеренное значение определяют в холодном и без давления состоянии арматуры и сравнивают с определенным аналитически из функциональной модели арматуры значением для специфичной для арматуры величины. Для этого аналитически определенного значения устанавливают верхнее и нижнее граничное значения, которым поставлены в соответствие еще допустимые состояния арматуры (расчетные резервы). Производят индикацию эксплуатационной готовности арматуры, если измеренное значение лежит между верхним и нижним граничным значением. Это позволяет предсказать поведение арматуры при ее использовании. 5 з.п. ф-лы.

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10-01-1999 дата публикации

СПОСОБ И УСТРОЙСТВО ДЛЯ УЛЬТРАЗВУКОВОГО ОПРЕДЕЛЕНИЯ МЕСТОПОЛОЖЕНИЯ УТЕЧКИ

Номер: RU2124721C1
Принадлежит: Сименс АГ (DE)

Для ультразвукового контроля местоположения утечки в различных местах вдоль измерительного участка измеряют уровни звука, вызванного утечкой. На измерительном участке определяют частичные участки с единым затуханием. Для определения местоположения утечки используют полосовую диаграмму уровней звука, в которой каждая из линий построена в пределах отрезка, длина которого определена произведением длины и затухания соответствующего частичного участка. Координату ее определяют умножением расстояния от начала частичного участка до соответствующего места измерения на коэффициент затухания. Местоположение утечки определяют делением значения координаты точки пересечения прямых, проведенных через конечные точки линий на диаграмме уровней звука на коэффициент затухания соответствующего частичного участка. Технический результат - повышение точности определения местоположения утечки. 2 с. и 2 з. п. ф-лы, 2 ил.

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10-09-2012 дата публикации

СИСТЕМА АКУСТИЧЕСКОГО КОНТРОЛЯ ТЕЧИ ТРУБОПРОВОДОВ АЭС

Номер: RU120276U1

... 1. Система акустического контроля течи трубопроводов, покрытых цилиндрической блочной съемной тепловой изоляцией, установленной аксиально трубопроводу с образованием кольцевой воздушной полости между поверхностью трубопровода и внутренней поверхностью изоляции, содержащая электрически связанные по меньшей мере два микрофона и электронный блок обработки сигналов, отличающаяся тем, что система включает в себя по меньшей мере две цилиндрические втулки, каждая из которых снабжена фиксирующим фланцем, закрепленным на верхнем торце втулки, при этом втулки установлены вдоль центральной оси трубопровода на толщину изоляции, а центральная ось каждой втулки расположена радиально относительно центральной оси трубопровода, корпус каждого микрофона выполнен цилиндрическим и снабжен цилиндрическим упорным фланцем, жестко закрепленным соосно на цилиндрической поверхности корпуса микрофона, каждый микрофон установлен в соответствующей втулке и соединен с ней по привалочным плоскостям соответствующих фланцев ...

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16-06-2022 дата публикации

Способ измерения прогиба протяженного вертикально направленного канала

Номер: RU2774260C1

Изобретение относится к способу измерения прогиба протяженных вертикально направленных каналов. Способ включает размещение внутри канала закрепленного на конце гибкой полой несущей штанги, по крайней мере, одного волоконно-оптического датчика, подачу светового сигнала по подключенным к датчику волоконно-оптическим линиям, регистрацию отраженных световых сигналов с помощью соединенного с волоконно-оптическими линиями фотоприемника. Затем определяют прогиб канала на основе анализа параметров светового сигнала с помощью подключенного к фотоприемнику компьютера. Причем волоконно-оптический датчик снабжают гравитационным маятником, фиксируют сдвиг интерференционной картины отраженного светового сигнала в газовом зазоре между верхней торцевой поверхностью гравитационного маятника и нижней торцевой поверхностью соединенных с фотоприемником и закрепленных на датчике волоконно-оптических линий, изменяющемся при перемещении волоконно-оптического датчика за счет отклонения гравитационного маятника ...

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20-02-1999 дата публикации

СПОСОБ И УСТРОЙСТВО ДЛЯ УЛЬТРАЗВУКОВОГО ОПРЕДЕЛЕНИЯ МЕСТОПОЛОЖЕНИЯ УТЕЧКИ

Номер: RU2126537C1
Принадлежит: Сименс АГ (DE)

Для ультразвукового определения местоположения утечки в различных местах вдоль измерительного участка измеряют уровни звука, вызванного утечкой. Местоположение утечки определяют на полосовой диаграмме уровней звука. Для кольцевой структуры полосовую диаграмму формируют из полосовой диаграммы уровней звука на указанном участке и пристроенной к ней второй такой же полосовой диаграммы Выделяют соответствующий измерительному участку отрезок диаграммы с полосой, соответствующей максимальному уровню звука, в середине. Имеется устройство обработки данных, выполненное с возможностью формирования указанной полосовой диаграммы с выделением отрезка, на котором определяют местоположение утечки. Возможно осуществление коррекции значения уровня звука для компенсации наложения звуковых колебаний, возникающих из-за утечки с противоположных от него сторон. Изобретение направлено на повышение точности определения местоположения утечки. 2 н.з. и 3 з.п.ф-лы, 4 ил.

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29-11-2021 дата публикации

Канал измерительный акустический

Номер: RU2760604C1

FIELD: nuclear energy. SUBSTANCE: invention relates to the field of nuclear energy and can be used, in particular, in systems for detecting, locating and determining the amount of coolant leakage from pipelines and equipment of water-water energetic reactors (WWER). The acoustic measuring channel contains an acoustic sensor 1 connected by means of a connection node with an analog communication line 2 connected to the input of an amplifier-converter 12, the output of which is connected to the input of an information device 13 by means of a digital communication line 16. The channel is equipped with an acoustic communication line, including the first and second waveguides 4, 5 connected to each other by means of the first quick-release connector 8 and connected to each other by means of the second quick-release connector 11, half-clamps 6 and 7 for tight installation on the controlled pipeline 10. The first waveguide 4 is rigidly connected to the acoustic sensor 1, the second waveguide 5 is rigidly connected to one of the half-clamps 6, and the connection node is made in the form of a detachable connector 3, the instrument part of which is connected to the acoustic sensor 1, and the cable part is connected to the analog communication line 2. EFFECT: increase in the safety of operation of the measuring channel, to reduction in the dose loads on the operating personnel when servicing the measuring channel. 3 cl, 1 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 760 604 C1 (51) МПК F17D 5/02 (2006.01) G21C 17/017 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК F17D 5/02 (2021.08); G21C 17/017 (2021.08) (21)(22) Заявка: 2021109291, 05.04.2021 (24) Дата начала отсчета срока действия патента: Дата регистрации: 29.11.2021 (45) Опубликовано: 29.11.2021 Бюл. № 34 Адрес для переписки: 121165, г. Москва, Г-165, а/я 15, ЮСТИС, Грунин Ефим Валерьевич (73) Патентообладатель(и): Акционерное общество «Научно-технический центр « ...

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27-11-2006 дата публикации

СПОСОБ И СИСТЕМА АНАЛИЗА И ОЦЕНКИ БЕЗОПАСНОСТИ ТЕХНОЛОГИЧЕСКОГО ПРОЦЕССА

Номер: RU2005116169A
Принадлежит:

... 1. Способ анализа и оценки безопасности технологического процесса с использованием устройства обработки данных, включающий сбор и анализ исходной информации, определение критериев безопасности, моделирование и проведение качественного и количественного анализа безопасности, отличающийся тем, что в качестве критериев безопасности технологического процесса выбирают превышения допустимых воздействий; выявляют на основе анализа технологического процесса в качестве источников опасности такие нарушения технологического процесса и условий эксплуатации, которые могут привести к превышению указанных допустимых воздействий; проводят анализ распределения зон действия выявленных источников опасности по различным частям технологического процесса и определяют в качестве интервалов безопасности технологического процесса такие части, для которых остаются неизменными условия безопасности технологического процесса; проводят анализ перехода нарушений технологического процесса из одного интервала безопасности ...

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10-12-2015 дата публикации

УСТРОЙСТВО НАКОПЛЕНИЯ, ОТОБРАЖЕНИЯ И ОТВОДА ВОЗДУХА ДЛЯ ИСПОЛЬЗОВАНИЯ В ЯДЕРНОЙ ПРОМЫШЛЕННОСТИ

Номер: RU2570304C1
Принадлежит: НЬЮККОРП, ИНК. (US)

Устройство для накопления, изоляции, отображения и отвода накопленного газа в трубе системы с текучей средой включает в себя основное трубное соединительное устройство, прикрепленное к трубе системы, в которой просверлено отверстие. Вертикальная труба, прикрепленная к трубному соединительному устройству, вмещает в себя магнитный поплавок. Индикатор уровня магнитного поплавка снаружи трубы отображает уровень магнитного поплавка. Клапан, прикрепленный к вертикальной трубе над магнитным поплавком, обеспечивает управляемый отвод газа из вертикальной трубы и, таким образом, из системы трубопроводов. Газ из трубы системы, накапливающийся в вертикальной трубе, удаляется из первичного пути потока текучей среды трубы системы. В вертикальной трубе, по мере снижения поверхности раздела жидкости/газа, поплавок опускается до заданного уровня, при котором пользователь отводит газ из системы трубопроводов, заставляя магнитный поплавок подниматься, отображая, что газ в системе трубопроводов снова находится ...

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10-12-2014 дата публикации

СПОСОБ И УСТРОЙСТВО ДЛЯ НЕПРЕРЫВНОГО КОНТРОЛЯ ИЗГИБА ТРУБЫ ТЕХНОЛОГИЧЕСКОГО КАНАЛА

Номер: RU2013125879A
Принадлежит:

... 1. Способ для непрерывного контроля изгиба трубы, включающий выставление механического датчика перемещения на нулевую отметку перед началом контроля, размещение гибкой измерительной штанги в разгруженном технологическом канале, создание в канале условий работающего реактора, изменение формы штанги, срабатывание механического индикатора, регистрация показаний датчика перемещения, отличающийся тем, что при размещении измерительной штанги в непрямолинейном технологическом канале и изменении межсекционного изгиба измерительной штанги в заранее выбранном стыке на угол α переводят межсекционный изгиб в линейное смещение Δ конца части секции, свободно заходящего внутрь сопрягаемой секции на длину L, при этом Δ=α*L, при помощи механической связи смещение Δ переводят в пропорциональное смещение датчика перемещения; после запуска реактора и продолжении искривления трубы контролируют динамику относительного смещения механического индикатора и определяют текущий изгиб контролируемой трубы, в т.ч. в ...

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10-10-2008 дата публикации

ГИБКИЙ ШТОК В СБОРЕ ВРАЩАЮЩЕГОСЯ ЗОНДА

Номер: RU2007110967A

ÐÎÑÑÈÉÑÊÀß ÔÅÄÅÐÀÖÈß (19) RU (11) 2007 110 967 (13) A (51) ÌÏÊ G21C 17/017 (2006.01) ÔÅÄÅÐÀËÜÍÀß ÑËÓÆÁÀ ÏÎ ÈÍÒÅËËÅÊÒÓÀËÜÍÎÉ ÑÎÁÑÒÂÅÍÍÎÑÒÈ, ÏÀÒÅÍÒÀÌ È ÒÎÂÀÐÍÛÌ ÇÍÀÊÀÌ (12) ÇÀßÂÊÀ ÍÀ ÈÇÎÁÐÅÒÅÍÈÅ (21), (22) Çà âêà: 2007110967/06, 07.03.2005 (71) Çà âèòåëü(è): ÈÍÅÒÅÊ-ÈÍÑÒÈÒÜÞÒ ÔÎ ÍÓÊËÅÀ ÒÅÕÍÎËÎÄÆÈ Ä.Î.Î. (HR) (30) Êîíâåíöèîííûé ïðèîðèòåò: 07.03.2005 HR P20050220A (43) Äàòà ïóáëèêàöèè çà âêè: 10.10.2008 Áþë. ¹ 28 (72) Àâòîð(û): ÃÐÀÑÈÍ Ðåíàòî (HR) (87) Ïóáëèêàöè PCT: WO 2006/095208 (14.09.2006) Àäðåñ äë ïåðåïèñêè: 117279, Ìîñêâà, óë. Ìèêëóõî-Ìàêëà , 55À, ÇÀÎ "ÔÈÐÌÀ "ÖÅÍÒÐ ÏÀÒÅÍÒÍÛÕ ÓÑËÓÃ", ïàò.ïîâ. Å.À.Õàð÷åíêî R U (57) Ôîðìóëà èçîáðåòåíè 1. Ãèáêèé øòîê â ñáîðå âðàùàþùåãîñ çîíäà ñ âûñîêèì ïîêàçàòåëåì ãèáêîñòè ñ âîçìîæíîñòüþ ïðîòàëêèâàíè -âûò ãèâàíè è îäíîâðåìåííîãî âðàùåíè , îòëè÷àþùèéñ òåì, ÷òî îí èìååò ãèáêèé øòîê äèàìåòðîì 3,2 ìì (äîïóñê ±0,1 ìì), èçãîòîâëåííûé èç 4 èëè 5 ñëîåâ ïðî÷íîé íà ðàçðûâ ïðîâîëîêè, ïðè÷åì øòîê ðàññ÷èòàí íà äåôîðìàöèþ ïðè ìàëîì âðàùàþùåì ìîìåíòå. 2. Ãèáêèé øòîê â ñáîðå âðàùàþùåãîñ çîíäà ïî ï.1, îòëè÷àþùèéñ òåì, ÷òî îí èìååò äâà êîàêñèàëüíûõ êàáåë äèàìåòðîì 0,5 ìì òèïà AWG40, ìíîãîæèëüíûå 40- èëè 50-îìíûå, íàìîòàííûõ íà ãèáêèé øòîê. 3. Ãèáêèé øòîê â ñáîðå âðàùàþùåãîñ çîíäà ïî ï.2, îòëè÷àþùèéñ òåì, ÷òî êîàêñèàëüíûå êàáåëè ïðèêðåïëåíû ê øòîêó ÷åðåç êàæäûå 50 ìì òåðìîóñàæèâàþùèìèñ òðóáêàìè äèàìåòðîì 6 ìì, äëèíîé 4 ìì, ïîêðûòûìè èçíóòðè êëååì, ñ êîýôôèöèåíòîì óñàäêè 3:1. 4. Ãèáêèé øòîê â ñáîðå âðàùàþùåãîñ çîíäà ïî ëþáîìó èç ïï.2 è 3, îòëè÷àþùèéñ òåì, ÷òî ïîâåðõ øòîêà è êàáåëåé óñòàíîâëåí ãèáêèé íåéëîíîâûé ðóêàâ èç ìàòåðèàëà, íàïðèìåð íåéëîí 66-nylaflow, äèàìåòð 7,93/5,9 ìì. 5. Ãèáêèé øòîê â ñáîðå âðàùàþùåãîñ çîíäà ïî ï.1, îòëè÷àþùèéñ òåì, ÷òî îí èìååò ïîäøèïíèê â ñáîðå. Ñòðàíèöà: 1 RU A 2 0 0 7 1 1 0 9 6 7 A (54) ÃÈÁÊÈÉ ØÒÎÊ Â ÑÁÎÐÅ ÂÐÀÙÀÞÙÅÃÎÑß ÇÎÍÄÀ 2 0 0 7 1 1 0 9 6 7 (86) Çà âêà PCT: HR 2005/000019 (07.03.2005) R U (85) Äàòà ïåðåâîäà çà âêè PCT íà íàöèîíàëüíóþ ôàçó: 27.03.2007

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30-04-1987 дата публикации

Номер: DE0002635537C2

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03-12-1981 дата публикации

ZYLINDRISCHE FUEHRUNGSSCHIENE FUER EINEN DETEKTOR

Номер: DE0003102992A1
Принадлежит:

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29-03-1996 дата публикации

Support plate inspection device

Номер: OA0000009995A
Принадлежит:

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25-02-1982 дата публикации

TEST MANIPULATOR FOR THE EXTERNAL EXAMINATION OF PIPINGS, PREFERABLY TO ULTRASONIC EXAMINE WITH REACTOR PRESSURE VESSELS

Номер: AT0000365836B
Автор:
Принадлежит:

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15-06-1981 дата публикации

PRUEFMANIPULATOR ZUR AUSSENPRUEFUNG VON ROHRLEITUNGEN, VORZUGSWEISE ZUM ULTRASCHALL-PRUEFENBEI REAKTORDRUCKBEHAELTERN

Номер: ATA269178A
Автор:
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15-06-1981 дата публикации

TEST MANIPULATOR FOR THE EXTERNAL EXAMINATION OF PIPINGS, PREFERABLY TO ULTRASONIC EXAMINE WITH REACTOR PRESSURE VESSELS

Номер: AT0000269178A
Автор:
Принадлежит:

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15-02-1996 дата публикации

SELFPROPELLED JOINT VEHICLE WITH TELESCOPIC PRESSURE CYLINDERS FOR TUBING INSPECTION

Номер: AT0000134257T
Принадлежит:

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14-06-1983 дата публикации

DEVICE FOR THE INSPECTION OF WELDS

Номер: CA0001148249A1
Автор: DIJKSTRA DURK
Принадлежит:

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14-05-2005 дата публикации

DIAMETRIC EXPANSION MEASUREMENT

Номер: CA0002449523A1
Принадлежит:

This paper describes a method for measuring the diametral expansion of the pressure tubes at Gentilly-2 nuclear generating station. The aim is to describe the solution, the calibration tools, and the analytical methods developed for the project. To measure the diametral expansion of the pressure tubes, Hydro-Québec modified the SLARette device and integrated a new module called MED. The measurement system is made up of three parts: 1. An inspection head, the MED (Hydro-Québec) module, which has five ultrasonic probes that determine the distance between the inspections head and pressure tube. Measurements are always done under water and they are used to determine the diameter and thickness of the pressure tubes. 2. A Tomoscan III acquisition system by R/D Tech to scan the five probes and save the data in an A-scan file. 3. An Analytical software: LogaMED (Hydro-Québec). The advanced delivery machine (ADM) equipped with a SLARette device is primarily an axial inspection system. The ADM and ...

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15-07-2012 дата публикации

METHODS FOR CALANDRIA TUBE SHEET BORE PREPARATION, CLEANING, AND INSPECTION FOR USE IN RETUBING OF A NUCLEAR REACTOR

Номер: CA0002766476A1
Принадлежит:

A method of preparing a calandria tube sheet bore for receiving a calandria tube. The method includes the steps of polishing the bore of the calandria tube sheet; and inspecting the bore, wherein the steps of polishing the bore and inspecting the bore are repeated if there are geometric deviations from a uniform engineered surface in the bore that provide a potential leak pathway in the final fabricated joint.

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07-03-1989 дата публикации

SENSOR FEED SYSTEM

Номер: CA1250964A

SENSOR FEED SYSTEM A sensor feed system suitable for use within the heavily irradiated environment of a nuclear reactor provides for the controlled displacement of a sensor in monitoring relation along a substantially horizontal tube associated with the reactor. The system has a piston for travelling along the tube, with laterally scanning sensor means carried by the piston. A pressurized fluid supply connected in sealing relation with one end of the tube serves, in use, to displace the piston inwardly along the tube. A flexible tether attached at one end to the piston is used to release and retract the piston, by way of a coiling drum provided with a drive to selectively rotate the drum, with axial positioning provision for the drum for maintaining alignment of the tether with the tube, and tether tension sensing provision connected in controlling relation with the drum when operating in a tether-releasing sense, to maintain the tension acting on the tether at or above a predetermined ...

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30-09-2001 дата публикации

METHOD OF GENERATING WALL-THICKNESS THINNING PREDICTION INFORMATION, AND COMPUTER-READABLE RECORDING MEDIUM STORING WALL-THICKNESS THINNING PREDICTION PROGRAM, AND METHOD OF PLANNING PIPING WORK PLAN

Номер: CA0002342655A1
Принадлежит:

A method of generating wall-thickness thinning prediction information where a wall-thickness thinning rate at a given position is estimated using information having a small number of measured points. Simulation of behavior of fluid flowing inside a pipe line is performed based on wall-thickness data of pipes and three-dimensional layout data of the pipe line. Simulated wall-thickness thinned data of the pipes of the pipe line are calculated from changes of the simulated behavior of fluid. The thinning rate prediction data is used to generate a plan for replacing the pipes based on the estimated wall thickness.

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08-06-2004 дата публикации

METHOD OF GENERATING WALL-THICKNESS THINNING PREDICTION INFORMATION, AND COMPUTER-READABLE RECORDING MEDIUM STORING WALL-THICKNESS THINNING PREDICTION PROGRAM, AND METHOD OF PLANNING PIPING WORK PLAN

Номер: CA0002342655C
Принадлежит: HITACHI, LTD.

A method of generating wall-thickness thinning prediction information where a wall-thickness thinning rate at a given position is estimated using information having a small number of measured points. Simulation of behavior of fluid flowing inside a pipe line is performed based on wall-thickness data of pipes and three-dimensional layout data of the pipe line. Simulated wall-thickness thinned data of the pipes of the pipe line are calculated from changes of the simulated behavior of fluid. The thinning rate prediction data is used to generate a plan for replacing the pipes based on the estimated wall thickness.

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08-10-2019 дата публикации

IMPROVED ULTRASOUND INSPECTION

Номер: CA0002934164C

A device and method for performing ultrasound scanning of a substantially cylindrical object, the device comprising a cuff adapted to fit around a circumference of the object, an ultrasound probe mounted about the inner circumference of the cuff and positioned to scan the circumference of the object, and one or more data connections providing control information for the ultrasound probe and receiving scanning data from the ultrasound probe. The probe includes one or more sensors to determine its orientation or location, and this data is used to control the operation of the device and to process data from the array.

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14-07-2012 дата публикации

METHOD FOR REMOVAL OF PRESSURE TUBES AND CALANDRIA TUBES FROM A NUCLEAR REACTOR

Номер: CA0002727492A1
Принадлежит:

A calandria tube, a pressure tube, and first and second end fittings joined to opposing end portions of the pressure tube, are removed from the calandria of a nuclear reactor by first cutting through the pressure tube inboard of each of first and second bell shaped end portions of the calandria tube to form a main pressure tube portion between first and second severed pressure tube end portions. The first and second end fittings together with the respective joined first and second severed pressure tube end portions are removed. The calandria tube is cut outboard of the main pressure tube portion and inboard of the second bell shaped end portion to form a main calandria tube portion, and a severed calandria tube end portion. The main calandria tube portion together with the main pressure tube portion are then removed from the calandria. The severed calandria tube end portion is also removed from the calandria.

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04-10-2012 дата публикации

PROFILING TOOL FOR DETERMINING MATERIAL THICKNESS FOR INSPECTION SITES HAVING COMPLEX TOPOGRAPHY

Номер: CA0002831812A1
Принадлежит:

A phased array ultrasonic probe may be mounted to a component to be inspected for wall thickness on an apparatus that includes a split ring adapted to be magnetically held in place on the component. In particular, the probe may be mounted to a carriage connected to the split ring in a manner that allows the carriage to rotate around the split ring while the probe is in operation. Between the probe and the component, a transducer shoe defining, by a flexible membrane, a cavity and an aperture. Conveniently, the construction of the flexible membrane allows wall thickness measurements to be acquired in portions of the component that have complex topography, such as welds. The apparatus is installed on an adaptor assembly for inspection of straight section of pipes. This adaptor assembly is not used in absence of straight section. By acquiring data from multiple output pulse transmitted at multiple incidence angles, processing software may conveniently produce an accurate wall thickness map ...

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04-10-2012 дата публикации

CALANDRIA TUBE JOINT

Номер: CA0002831608A1
Принадлежит:

The present invention relates to a method of refurbishing calandria vessels in nuclear reactors, and more specifically, to a method of fastening calandria tubes to a tubesheet plate in a calandria when refurbishing a nuclear reactor. A method of refurbishing a calandria is described, comprising the steps of: forming circumferential cuts/serrations/grooves on the outside diameter of a calandria tube; and expanding/deforming the calandria tube into a bore of a tubesheet plate of the calandria, whereby the sharp edges of the serrations "bite" into the tubesheet plate to provide a leak- tight seal. Other aspects of the invention are also described.

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14-11-2013 дата публикации

INCORE INSTRUMENTATION CABLE ROUTING AND SUPPORT ELEMENT FOR PRESSURIZED WATER REACTOR

Номер: CA0002870719A1
Принадлежит:

A nuclear reactor comprises a pressure vessel, a nuclear reactor core comprising fissile material disposed in the pressure vessel, and a core basket disposed in the pressure vessel and containing the nuclear reactor core. An incore instrument is disposed in a guide tube of the nuclear reactor core. The incore instrument has a cable extending out of the bottom of the nuclear reactor core and making a 180° turn. A bottom support element is attached to the bottom of the core basket and defines or includes a routing tube that routes the cable of the incore instrument through the 180° turn. In some embodiments, the pressure vessel includes upper and lower vessel portions, the nuclear reactor core and core basket are disposed in the lower vessel portion, and the vessel penetration is through the lower vessel portion or through a mid-flange connecting the upper and lower vessel portions.

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20-02-1994 дата публикации

METHOD AND APPARATUS FOR CALIBRATING AN ULTRASONIC LEAK LOCATION

Номер: CA0002104325A1
Принадлежит:

A method for ultrasonic leak location includes showing ultrasound levels measured at various measuring locations along a measuring segment in a bar diagram. An intersection of two straight lines in the bar diagram is ascertained to identify a leakage position. At least an individual ultrasound pickup is calibrated with respect to its amplification factor and/or its location error. An apparatus for ultrasonic leak location includes a number of ultrasound pickups being disposed along a measuring segment. Amplifiers and components forming an effective value connect outputs of the ultrasound pickups to a data processing system. The data processing system calibrates an individual ultrasound pickup with respect to its amplification factor and/or its location coordinate.

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18-04-1996 дата публикации

Tube Extractor

Номер: CA0002155271A1
Принадлежит:

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09-03-1997 дата публикации

FUEL BUNDLE POSITION VERIFICATION TOOL

Номер: CA0002157812A1
Принадлежит: OLDHAM, EDWARD H.

This invention relates to a device which is used in conjunction with a CANDU nuclear fueling machine to provide an indication of the precise location of a particular fuel bundle in a nuclear reactor.

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20-02-1994 дата публикации

METHOD AND APPARATUS FOR ULTRASONIC LEAK LOCATION

Номер: CA0002104322A1
Принадлежит:

A method for ultrasonic leak location includes showing sound levels at various measuring locations along a measurement segment, with a bar diagram. The same bar diagram is added again to the bar diagram. A particular sound level having the highest value and being located the most in the middle of the placed together bar diagrams is picked out. A segment around the associated pickup positions having one complete set of pickup positions is picked out. Two compensating straight lines for that set having an intersection being ascertained to identify the leakage position are determined. Another method includes providing at least a sound level having a position substantially facing the leakage position with a correction value. An apparatus for ultrasonic leak location includes a number of ultrasound pickups being disposed along a measuring segment. Amplifiers and components forming an effective value connect a data processing system to outputs of the ultrasound pickups. The data processing system ...

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15-06-1979 дата публикации

Номер: CH0000611708A5
Принадлежит: KRAFTWERK UNION AG

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15-06-1978 дата публикации

Номер: CH0000600337A5
Автор: GUGEL GEORG, GEORG GUGEL
Принадлежит: KRAFTWERK UNION AG

Подробнее
15-02-1978 дата публикации

Номер: CH0000595627A5
Принадлежит: GEN ELECTRIC, GENERAL ELECTRIC CO.

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31-08-2006 дата публикации

Inspection device for nuclear reactors.

Номер: CH0000695806A5
Принадлежит: GEN ELECTRIC, GENERAL ELECTRIC COMPANY

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15-08-2007 дата публикации

Camera mounting plate.

Номер: CH0000696613A5
Принадлежит: GEN ELECTRIC, GENERAL ELECTRIC COMPANY

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15-07-2009 дата публикации

Inspection probe for a drilling.

Номер: CH0000698311B1
Принадлежит: GEN ELECTRIC, GENERAL ELECTRIC COMPANY

Eine Sonde (100) zum Inspizieren einer Bohrung weist ein Gehäuse auf, das zum Einführen in die Bohrung abgemessen ist, sowie mehrere Stabilisierungsbeine (112), die ein erstes Ende (106), das an dem Gehäuse (101) angeordnet ist, und ein zweites Ende (108) aufweisen, das aus dem Gehäuse (101) ausfahrbar ist. Die Stabilisierungsbeine (112) sind dazu konfiguriert, in Kontakt mit der Innenfläche der Bohrung zu gelangen. Mehrere Sensorarme (116) sind von dem Gehäuse (101) ausfahrbar und relativ zu den Stabilisierungsbeinen (112) rotierbar. Ein Motor 111 sieht das Rotieren der Sensorarme (116) relativ zu den Stabilisierungsbeinen (112) vor.

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26-02-2010 дата публикации

System and procedure for shielding a radiation of a reactor container inner wall, whereby the radiation proceeds from contents, which are stored in the reactor container.

Номер: CH0000699373B1
Автор: PAO HSUEH-WEN
Принадлежит: GEN ELECTRIC, GENERAL ELECTRIC COMPANY

Die Erfindung betrifft ein System und ein Verfahren zum Abschirmen einer Strahlung von einer Reaktorgefässinnenwand, wobei die Strahlung von einem Inhalt ausgeht, der in dem Reaktorgefäss (12) gespeichert ist. Das Reaktorgefäss enthält Einlassdüsen (13), Auslassdüsen (14) und am Boden angebrachte Instrumente (15). Das Verfahren umfasst das Entfernen von Kernzylindern in dem Reaktorgefäss, das Installieren einer Spannungsabschirmung in dem Reaktorgefäss, das Installieren eines Kofferdamms, die Drainage des Reaktorgefässes, das Absenken eines Werkzeuglieferroboters in das Reaktorgefäss, das Anbringen des Werkzeuglieferroboters an einer Oberfläche des Reaktorgefässes, das Absenken einer Werkzeugwanne in das Reaktorgefäss und das Anbringen der Werkzeugwanne an der Oberfläche des Reaktorgefässes.

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15-06-2010 дата публикации

Procedure for bringing a tool into a dipped drilling.

Номер: CH0000700027B1
Принадлежит: GEN ELECTRIC, GENERAL ELECTRIC COMPANY

Ein Verfahren zum Einbringen eines Werkzeugs (120) in eine getauchte Bohrung umfasst das Steuern der Bewegung einer Werkzeugeinbringvorrichtung (100) in einem Becken durch das Bedienen von wenigstens einem Vorschubantrieb (108), der an der Werkzeugeinbringvorrichtung (100) angeordnet ist. Die Werkzeugeinbringvorrichtung (100) wird an einen Einlass der Bohrung gekoppelt, und ein Werkzeug (120) wird von der Werkzeugeinbringvorrichtung (100) durch den Einlass und in die Bohrung eingeführt.

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25-08-2005 дата публикации

СИСТЕМА РЕГИСТРАЦИИ ТЕЧЕЙ ТЕПЛОНОСИТЕЛЯ 1-ГО КОНТУРА РЕАКТОРНЫХ УСТАНОВОК АТОМНЫХ ЭЛЕКТРОСТАНЦИЙ (СРТ)

Номер: EA0200400933A1
Принадлежит:

Предлагаемое изобретение может быть использовано на всех реакторных установках атомных станций России с водо-водяными и водографитовыми реакторами. Задача изобретения заключается в обеспечении возможности обнаружения местонахождения и расхода течи теплоносителя 1-го контура РУ АС. Сущность изобретения состоит в том, что система включает блок контролируемых помещений с оборудованием 1-го контура реакторной установки, соединенного через воздуховоды вытяжной вентиляции с блоком каналов, предназначенных для измерения относительной влажности воздуха в контролируемых помещениях, включающим эталонный канал, предназначенный для измерения относительной влажности наружного воздуха в помещении с измерительными каналами. Датчики измерительных каналов соединены с блоком управления для регистрации и сравнения показателей относительной влажности воздуха в контролируемых помещениях и помещении с измерительными каналами. Предлагаемая система позволит с достаточной точностью и скоростью определить появление ...

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30-01-2008 дата публикации

Rotating probe flexible shaft assembly

Номер: CN0101116147A
Принадлежит:

Rotating probe flexible shaft assembly is used as carrier of eddy current rotating probe for tubing examination. Basically this invention is applied in assembly of eddy current rotating probe for examination of tubes in steam generators mounted in WWER type of nuclear power plant (13 mm inside diameter of tube). This assembly provides good flexibility, while maintaining feature to be pushed-pulled and rotated in the same time. Rotating probe flexible shaft assembly is determined by flexible shaft with diameter 3.2 mm. Two coaxial cables with diameter 0.5 mm are wounded around flexible shaft. Coaxial cables are fixed to the shaft every 50 mm by heated shrink tubes (raw 6x4 mm). Nylon hose 8/6 is mounted over flexible shaft and cables fixed with heated shrink tubes while putting grease on shrink tubes. Both sides of flexible shaft are ended with bearing assemblies.

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20-04-2016 дата публикации

Method for repair of regulator, and the apparatus used for implementing this method

Номер: CN0103649639B
Автор:
Принадлежит:

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23-06-2017 дата публикации

Process system piping arrangement method

Номер: CN0106887260A
Автор: LI MING
Принадлежит:

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02-01-2013 дата публикации

Low-discharging steam generator inspection detector

Номер: CN102855949A
Автор: J B Draper, L E Magee
Принадлежит:

The invention relates to a low-discharging steam generator inspection detector, particularly, an inspection assembly (10) for insertion inspection of an elongate hollow member. The inspection assembly (10) includes a probe head (28) including at least one sensor (36) for sensing a characteristic of the elongate hollow member as the probe head (28) is moved internally within the elongate hollow member. The assembly includes a flexible shaft (30) connected to the probe head (28) and transmitting a motive force to the probe head (28) to move the probe head (28) within the elongate hollow member. The flexible shaft (30) encloses at least one wire (42) operatively connected between the probe head (28) and at least one component external to the elongate hollow member for sensory operation of the at least one sensor (36). The flexible shaft (30) is at least partially corrugated.

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06-04-2016 дата публикации

Fire fighting water system of nuclear power plant and method for assembling system

Номер: CN0105469843A
Автор: WANG JINLONG, LIU HONGYONG
Принадлежит:

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22-09-1978 дата публикации

SELF-PROPELLED VEHICLE HAS ARM ARTICULATE

Номер: FR0002381657A1
Автор: JEAN VERTUT, VERTUT JEAN
Принадлежит:

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01-10-1999 дата публикации

PROCESS OF CLEANING OF the SECONDARY PART Of a STEAM GENERATOR Of a NUCLEAR REACTOR COOLED BY WATER UNDER PRESSURE

Номер: FR0002765720B1
Автор: TEXIER, GUILLERMIER, GENTIL
Принадлежит: AREVA NP

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12-02-1999 дата публикации

USE AND PROCESS AND SAMPLING DEVICE Of a SAMPLE IN a METAL WALL

Номер: FR0002756631B1
Автор:
Принадлежит:

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29-03-2002 дата публикации

Precision indication and tracking procedure for portions of pipe circuitry uses optical sighting, triangulation and scanning

Номер: FR0002814539A3
Автор: COURCOUX ALAIN
Принадлежит:

On détermine par visées optiques et triangulation la position d'un ensemble d'au moins trois cibles de repérage (12a, 12b, 12c, 13a, 13b, 13c) liées à l'environnement de la portion de circuit dont on effectue le relevé. On définit à partir des positions des cibles un repère virtuel orthonormé (11) et les coordonnées du centre des cibles dans le repère orthonormé. On réalise un balayage optique de la scène constituée par la portion de circuit et son environnement au moyen d'un faisceau laser associé à une caméra CCD. On détermine la position des centres de cibles centrées liées à l'environnement et de points représentatifs de la portion de circuit de tuyauteries. On détermine les coordonnées des points représentatifs de la portion de circuit dans le repère orthonormé virtuel (11), à partir des distances calculées et des coordonnées des centres des cibles centrées déterminées par visées optiques et triangulation. On effectue au moins un tracé de la portion de tuyauterie sous forme d'un plan ...

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31-01-1997 дата публикации

Sepn. measurement device for two surfaces - has ultrasonic transducer and inclined mirror with central window for splitting ultrasonic wavefront into two fractions

Номер: FR0002737295A1
Принадлежит:

Ce dispositif est caractérisé en ce qu'il comporte: - des moyens (2, 3) de génération d'un front d'ondes ultrasonores en direction de la première surface (S1); - des moyens (3, 4, 5) de division du front d'ondes ultrasonores en deux parties, pour engendrer deux échos, un premier écho après une simple réflexion sur la première surface (S1) et un second écho après réflexions successives sur la première surface, la seconde surface (S2) et à nouveau la première surface; - des moyens (2) de réception de ces échos; et - des moyens d'analyse de ces échos pour mesurer le décalage temporel entre ceux-ci et en déterminer la distance séparant les deux surfaces (S1, S2).

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15-01-1993 дата публикации

Method and device for checking a surface

Номер: FR0002679025A1
Принадлежит:

Selon ce procédé, un faisceau laser est conduit par une fibre optique (16) depuis une source (14) jusqu'à une tête laser (18) disposée au regard de la surface à contrôler (11). Celle-ci émet un faisceau réfléchi qui est renvoyé dans la fibre optique (16). Des faisceaux (Fi, Fr) prélevés sur le faisceau laser incident et sur le faisceau laser réfléchi sont convertis en signaux électriques (Si, Sr) qui sont envoyés dans un voltmètre différentiel à seuil (30). Les variations de mesure du voltmètre (30) par rapport à un seuil prédéterminé permettent de déceler des caractéristiques géométriques de la surface à contrôler. Application au contrôle du positionnement d'un manchon dans un tube et au contrôle du diamètre intérieur d'un tube.

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02-07-1999 дата публикации

PROCESS Of INSTALLATION OF the INTERNAL STRUCTURES Of a STEAM GENERATOR

Номер: FR0002773255A1
Автор: BLOCQUEL ALAIN
Принадлежит:

On introduit un premier dispositif d'usinage dans l'enveloppe externe (2) du générateur de vapeur (1) par un trou de visite (9) dans la partie supérieure de l'enveloppe externe (2), on met en place le premier dispositif d'usinage sur une partie supérieure de l'enveloppe de faisceau (4) renfermant le faisceau (3) du générateur de vapeur, on réalise par usinage, au moins une ouverture de passage (16) à travers l'enveloppe de faisceau (4) dans sa partie supérieure, on introduit dans l'enveloppe de faisceau (4) par l'ouverture de passage (16), au moins un second dispositif d'usinage et on réalise, en utilisant le second dispositif d'usinage, par découpage de tubes du faisceau (3) et de parties (21, 22) des plaques-entretoises (6a, 6) un passage de cheminement (15) du moyen d'intervention vers une pluralité de zones d'intervention dans le faisceau de tubes (3) du générateur de vapeur (1).

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24-07-2009 дата публикации

SYSTEM AND PROCESS FOR THE CLEANING OF CRACKS IN STEAM GENERATORS.

Номер: FR0002926630A1
Принадлежит: AREVA NP INC

Un procédé est proposé pour nettoyer des crevasses (40) entre une pluralité de tubes (26) et une pluralité de plaques de support de tube (30, 31, 32, 33, 34, 35, 36, 37) supportant les tubes (26) dans un générateur de vapeur (20). Les étapes comportent à remplir un secondaire du générateur de vapeur (20) avec un solvant (79) jusqu'à un premier niveau au-dessus d'une première plaque de support de tube (30) destinée à être nettoyée, vider le solvant (79) jusqu'à un deuxième niveau plus bas que la première plaque de support de tube (30), et remplir à nouveau le secondaire du générateur de vapeur (20) avec le solvant (79) jusqu'à un troisième niveau au-dessus de la première plaque de support de tube (30). Un système de nettoyage (100) est également proposé.

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02-01-2015 дата публикации

TOGETHER WITH A LOCKING ARRANGEMENT OF TUBES, AND MAINTENANCE METHOD THEREFOR

Номер: FR0003007811A1
Принадлежит:

L'ensemble comprend un dispositif (40) de blocage en position des tubes les uns par rapport aux autres, avec au moins un premier bras (44), un axe de blocage (48) présentant une pluralité de surfaces d'appuis (50), l'axe de blocage (48) étant mobile entre une position de blocage des tubes chacun entre une desdites surfaces d'appui (50) et le premier bras (44), et une position de libération dans laquelle les tronçons (42) des tubes sont libres.

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06-09-2002 дата публикации

PROCEEDED OF STATEMENT AND TRACE Utmost precision Of AT LEAST a PORTION Of UNCIRCUIT HAS CONSTITUTES PIPINGS

Номер: FR0002814539B3
Автор: COURCOUX ALAIN
Принадлежит:

Подробнее
03-04-1998 дата публикации

PROCESS AND DEVICE OF MEASUREMENT OF DEFORMATION OF TUBE GUIDE

Номер: FR0002754053A1
Автор: DESCOT PASCAL, SAVIN ERIC
Принадлежит:

Pour mesurer la déformation d'un tube guide d'assemblage combustible nucléaire (14), on déplace horizontalement une sonde à courants de Foucault (38) de façon à la faire passer successivement sur un repère rectiligne vertical (42), métallique, et sur les tubes guides d'une première rangée de l'assemblage (14) maintenu vertical, on mesure le signal de sortie de la sonde et on mémorise les positions de la sonde (38) correspondant aux extrema du signal, par rapport audit repère; on reproduit cette étape à plusieurs altitudes sur la rangée, puis sur les autres rangées. On recommence les mêmes étapes avec un déplacement de la sonde (38) dans un sens orthogonal au premier. A partir des positions mémorisées, on calcule l'amplitude et la direction des écarts de position par rapport à la position nominale pour un tube rectiligne, à chacune des altitudes.

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29-12-2006 дата публикации

Engraved character imaging, e.g. for nuclear fuel assemblies, comprises illumination, differential treatment of image pairs and binary model production

Номер: FR0002887664A1
Автор: HUPONT NICOLAS
Принадлежит:

Un dispositif et un procédé permettant de révéler des caractères gravés utilisent quatre prises d'image différentes (Ibrut). Grâce au système selon l'invention, il est possible d'effectuer la reconnaissance des caractères à distance importante de l'objet, et/ou que l'objet conserve un déplacement relatif indépendant du contrôle d'image. Une reconnaissance de caractères peut être associée. Le procédé selon l'invention est particulièrement indiqué pour l'identification d'assemblages de combustible nucléaire et leur contrôle au moment de leur chargement dans le réacteur.

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27-03-2012 дата публикации

ABRASION LIFETIME EVALUATION METHOD OF A STEAM GENERATOR PLUGGED HEAT TRANSFER TUBE WHICH ELIMINATES A REGION IN WHICH AN EVALUATION PROCESS IS NOT POSSIBLE

Номер: KR1020120029677A
Принадлежит:

PURPOSE: An abrasion lifetime evaluation method of a steam generator plugged heat transfer tube is provided to easily perform an evaluation process by considering an exponential value of an exponential function for thickness change properties according to the abrasion of a heat transfer tube surface. CONSTITUTION: A curve fitting process is performed based on a thickness measurement value before plugging a heat transfer tube. A first curve is generated(S100). An evaluation result is acquired by evaluating validity of the curve fitting process(S200). A second curve is generated by correcting the first curve(S300). A tube plugged correction coefficient is calculated(S400). An abrasion lifetime estimation curve is computed for the plugged heat transfer tube. The abrasion lifetime is evaluated(S500). COPYRIGHT KIPO 2012 ...

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14-04-2014 дата публикации

Testing Apparatus for a Welding Part of Steam Genderater Tube

Номер: KR1020140044163A
Автор:
Принадлежит:

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20-02-2013 дата публикации

FLUID PRESSURE DIAGNOSTIC DEVICE OF A MAIN STREAM DISCHARGING VALVE DRIVING PART CAPABLE OF IMPROVING THE RELIABILITY OF THE DEVICE BY IMMEDIATELY DETERMINING ABNORMALITY OF COMPONENTS

Номер: KR1020130017141A
Автор: LEE, IN HEE
Принадлежит:

PURPOSE: A fluid pressure diagnostic device of a main stream discharging valve driving part is provided to immediately determine the abnormality of a hydraulic system by detecting the pressure variation of integral sections of the hydraulic system at the same time, and analyzing the same on real time in a driving part operating process. CONSTITUTION: A pressure sensor(10) detects the fluid pressure of a component. The pressure sensor is connected to TPs(test plug)(TP1~TP6) through a test plug connector(40). One side of the TP connector is connected to the TP. The other side of the TP connector is connected to a pressure sensor. A data conversion part(20) converts a signal, which is detected at the pressure sensor, into a digital signal. A display part(30) indicates the digital signal, which is converted at the data conversion part, in a screen. COPYRIGHT KIPO 2013 [Reference numerals] (1) Graphing program; (2) Excel file program; (20) Data conversion; (3) Analysis program; (A1,A2) Access ...

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04-06-2010 дата публикации

REMOTE VISUAL INSPECTION SYSTEM INSIDE A STEAM GENERATOR, CAPABLE OF EXECUTING MACROSCOPY BY USING A REMOTE CONTROL METHOD

Номер: KR1020100059346A
Принадлежит:

PURPOSE: A remote visual inspection system inside a steam generator is provided to inspect the inner room of a steam generator in real time in a safe external control room by installing a video camera which is moved by a remote control robot in high radiation control region. CONSTITUTION: A remote control robot is installed inside a steam generator(1) in a radiation control region. An video camera takes a photograph of a tube sheet or the state of a diaphragm(4). A camera control part is installed in the radiation control region in order to receive an image delivered from the video camera. A monitor(41) displays an image delivered through the camera control part. An operation control part(42) controls the zoom and the focus operation of the video camera in a remote way. COPYRIGHT KIPO 2010 ...

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25-07-1998 дата публикации

Номер: KR1998032365A
Автор:
Принадлежит:

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13-04-1999 дата публикации

Dispositivo e processo para reconhecimento de vazamento

Номер: BR9708472A
Автор:
Принадлежит:

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16-08-2009 дата публикации

Acoustic load mitigator

Номер: TW0200935451A
Принадлежит:

A system for reducing an acoustic load of a fluid flow includes a first pipe. The first pipe includes a first end and a second end and a first aperture and a second aperture, the first and second apertures being intermediate the first and second ends. A second pipe includes a first end and a second end and a third aperture intermediate the first and second ends. The second pipe is connected at its first end to the first pipe at the first aperture. A bypass pipe includes a first end connected to the second aperture of the first pipe and a second end connected to the third aperture of the second pipe. A method of reducing an acoustic load of a flow in a standpipe connected to a first pipe configured to carry a main flow includes providing a bypass flow from the first pipe to the standpipe.

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01-01-2009 дата публикации

Structure for suppressing flow vibration of instrumentation guide tube

Номер: TW0200901226A
Принадлежит:

A structure for suppressing flow vibration of an instrumentation guide tube, the structure being constructed such that an upper hole (37A) and a lower hole (37B) are formed at two upper and lower positions in a side face of the guide tube (27) and that a thimble tube (22) is pressed against the inner peripheral surface of the guide tube (27) by a difference between pressures of a cooling material in the inside and outside of the upper and lower hole (37A, 37B). Further, the structure desirably has an upper pressure regulation hole and lower pressure regulation hole formed at two upper and lower positions in a side face of an upper reactor core support column (21).; The upper and lower pressure regulation holes allow a cooling material, having flown from the upper end of the guide tube into the guide tube, to flow from the inside to the outside of the guide tube through a gap between the thimble tube and the upper hole, flow from the inside to the outside of the upper reactor core support ...

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23-11-2017 дата публикации

WORM ROBOT

Номер: WO2017197418A1
Принадлежит:

The invention relates to a worm robot (1), comprising a plurality of segments (2) which are arranged successively along a worm axis, wherein the segments (2) are designed to be expandable in the radial direction and are interconnected with the aid of connecting means (10, 11). According to the invention, the segments (2) are held in a variable distance to each other and can be swiveled in all directions relative to one another, wherein first drives (13) are provided for changing the distance between the segments (2) and for swiveling the segments (2) in all directions relative to one another.

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28-01-2016 дата публикации

SYSTEM AND METHOD FOR SIMULTANEOUS MULTI-TUBE INSPECTION OF VERTICAL TUBE BUNDLE SYSTEM

Номер: WO2016014697A9
Автор: TRIPATHY, Kishlay
Принадлежит:

A multi-tube inspection system with a reel (36) having a plurality of cameras (20) is placed in the upper header (18). Each camera (20) is attached to its own lead line (28) and has a light source (22). An inspector (24), located in the upper header (18), aligns each camera (20) with a tube (14) and then operates the reel (36) to simultaneously lower the cameras (20) through their respective tube (14). As the cameras (20) pass through the tubes (14), they capture a video image of the interior length of the tube (14). The video image is stored and relayed to a control center (46) where additional inspectors (48) can review the video image of the interior of the tube (14). Each video is identified and tied back to the tube (14) in a data base. If a defect is identified, the tube (14) can be taken out of service (blocked off) or scheduled for cleaning. Once cleaned, the tube (14) is then reinspected.

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22-09-2011 дата публикации

SHUT-OFF DEVICE FOR A FLUID DUCT, USEFUL FOR EXAMPLE IN A NUCLEAR POWER STATION, IN PARTICULAR FOR SHUTTING-OFF A STEAM GENERATOR BOTTOM DRAIN

Номер: WO2011114077A3
Принадлежит:

The shut-offdevice (27) for a nuclear reactor component duct comprises: - a plurality of elastic sealing rings (41), each expandable radially with respect to a common longitudinal axis between a retracted position at a distance from a wall of the duct and an expanded position for leaktight contact with the wall of the duct; - a device designed to selectively move the sealing rings (41) between their retracted positions and their expanded positions; - at least one member (43) for locking in position the shut-off device (27) in the duct to be shut off, which member is separate from the sealing rings (41) and is expandable radially with respect to the central axis between a retracted position in which the locking member (43) is moved away from the wall of the duct and a locking position in which the locking member bears against the wall of the duct; - a device designed to selectively move the locking member (43) between its retracted position and its locking position. Figure 3 ...

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20-07-1995 дата публикации

DUAL GUIDE TUBE FOR INSPECTION OF HEAT EXCHANGERS

Номер: WO1995019526A1
Принадлежит:

A method and apparatus for simultaneously inspecting the inner wall of two tubes, such as in a heat exchanger, including a base member which supports first and second guide tubes for guiding inspection probes of a testing system. The guide tubes are held by the base member a predetermined distance apart to align with a pair of tubes of the heat exchanger. The guide tubes may be fixed with respect to the base member by clamping collars and spacer bushings, or may be mounted for longitudinal movement with respect to the base member against the bias of a coil spring. A robotic tool delivery system is used to automatically move the dual guide tube assembly through a predetermined sequence to optimize testing positions where two testing probes may be used simultaneously.

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25-07-1995 дата публикации

Device and method for monitoring the internal surface of a tubular piece

Номер: US0005436944A1
Принадлежит: Framatome

The device includes a first tubular support (11) carrying on its outside surface means for fixing to a handling tool, a second tubular support (18) mounted coaxially inside the first support (11) for rotation about its axis. A flexible strip (55) carrying a monitoring probe at one of its ends is engaged in a slideway support carried by the second support (18) and including an end part (65) mounted to pivot about an axis which is perpendicular to the axis (25) of the second support (18). The strip (55) is moved translationally along the axial direction (25) by a conveyor bolt (53). The inside surface of the tubular piece (3) is monitored by moving the probe fixed to the end of the flexible strip (55) rotationally about the axis (25) and in axial translation, inside the annular space (8) between the sleeve (5) and the tubular piece (3).

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08-03-2016 дата публикации

Method of providing and evaluating a mid-wall repair

Номер: US0009281085B2
Принадлежит: AZZ WSI LLC

A method of repairing a connection between a first nozzle and a closed vessel includes cutting through an entire thickness of the first nozzle at a location adjacent to the mid-wall of the vessel. A portion of the first nozzle is removed. A replacement nozzle is disposed in a void formed by removal of the portion of the first nozzle. A weld is formed between the replacement nozzle and a surface of the mid-wall of the vessel.

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22-04-2015 дата публикации

EDDY CURRENT INSPECTION PROBE

Номер: EP2862179A1
Принадлежит:

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26-04-1995 дата публикации

TESTING ARRANGEMENT FOR MATERIALS TESTING, PARTICULARLY IN A PRESSURIZED-WATER REACTOR

Номер: EP0000649559A1
Автор: ANDERSSON, Björn, H.
Принадлежит:

A testing arrangement (14) and a method for materials testing at lead-throughs in a cap of a pressurized-water reactor, comprising a flexible sword (85) which at one end is equipped with a probe. Since the lead-throughs consist of a first tube passing the cap and welded to it, and a second tube inserted in the first tube, the weld joint has to be inspected from below via a gap between the tubes. In order to do this by means of a manipulator, a pinching arrangement (32) is arranged, which by pressing the inner tube towards one side widens the gap at the opposite side so that the sword can be inserted. The pinching arrangement and the sword can then be displaced so that the sword and the widened gap moves around the inner tube, in order that the whole weld and its surrounding area can be inspected.

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03-05-1995 дата публикации

Diagnostic system responsive to learned audio signatures

Номер: GB0009505193D0
Автор:
Принадлежит:

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12-01-2012 дата публикации

Low row steam generator inspection probe

Номер: US20120006133A1
Принадлежит: General Electric Co

An inspection assembly for insertion inspection of an elongate tubular member. The inspection assembly includes a probe head with a sensor. The assembly also includes a flexible shaft connected to the probe head and transmitting a motive force to the probe head to move the probe head within the elongate tubular member. The probe head includes at least one characteristic to minimize resistance against movement of the probe head along a torturous path within the tubular member.

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11-10-2012 дата публикации

Repair device and repair method

Номер: US20120257937A1
Автор: Ken Onishi
Принадлежит: Mitsubishi Heavy Industries Ltd

This repair device includes a casing, a slide shaft slidably arranged with respect to the casing, a turn table rotatably arranged with respect to the slide shaft, a cutting mechanism installed on the turn table and including a cutting tool, and an advancing and retracting mechanism that displaces a radius of rotation of the cutting mechanism with respect to rotations of the turn table forward and backward. In a state where the casing is centered and positioned with respect to the pipe, the turn table is rotationally displaced while the slide shaft slides in an axial direction, and the advancing and retracting mechanism displaces the cutting mechanism forward and backward. Accordingly, the cutting tool helically turns along an inner peripheral shape of the pipe to cut an inner periphery of the pipe.

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23-05-2013 дата публикации

Preventive Maintenance Apparatus and Preventive Maintenance Method for Inner Surface of Piping

Номер: US20130125929A1
Принадлежит:

A preventive maintenance apparatus has a movable body and a water jet peening apparatus (WJP apparatus). The movable body installs a jet nozzle for driving and floating bodies on a base body. The movable body suspended in cooling water in a reactor pressure vessel jets high-pressure water from a high-pressure pump from the jet nozzle, advances in the cooling water, and is inserted into a pipe with the cooling water filled which is connected to the reactor pressure vessel. The posture of the movable body in the pipe is controlled by buoyancy adjustment of the floating bodies and the movable body can easily pass through a curve pipe portion. The high-pressure water from a high-pressure pump is jetted from jet nozzles of the WJP apparatus and for the inner surface of a vertical pipe portion, the WJP is executed. 1. A preventive maintenance apparatus comprising:a base body;a driving apparatus installed on said base body for advancing said base body;a water jet peening apparatus installed on said base body;a plurality of first floating bodies respectively installed at a leading portion and on a rear of said base body;a plurality of clamp apparatuses installed on said base body for making contact with an inner surface of a piping when holding said base body in said piping; anda camera installed on said base body.2. The preventive maintenance apparatus according to claim 1 , comprising:an air supply apparatus installed on said base body and communicated with each of said plurality of first floating bodies; anda buoyancy adjusting apparatus installed on said air supply apparatus for regulating respective air pressures in said plurality of first floating bodies.3. The preventive maintenance apparatus according to claim 1 ,wherein said driving apparatus has a first jet nozzle installed on said rear of said base body for jetting pressurized water; andwherein said water jet peening apparatus has a water jet peening bubble generation apparatus for generating water jet peening ...

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19-09-2013 дата публикации

Nozzle Inspection Tool for Nuclear Power Plants

Номер: US20130243145A1
Принадлежит: IHI Southwest Technologies Inc

A device is provided to inspect welds in nozzles located in water within a containment vessel of a nuclear power plant. A computer connected to the device controls movement by use of thrusters located along a main rail while buoyancy packs regulate the depth. After the device is navigated to a weld needing inspection, feet extend radially outward from the main rail to secure the device in the nozzle. Then transducer clusters are moved along the main rail to be radially inside the weld to be inspected. Thereafter, the transducer clusters are extended radially outward and rotated adjacent to the weld while simultaneously emitting test signals and receiving reflected signals to indicate the condition of the weld.

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19-12-2013 дата публикации

Eddy current inspection probe

Номер: US20130335111A1
Принадлежит: Westinghouse Electric Co LLC

A probe for transporting a nondestructive inspection sensor through a tube, that employs wheels to reduce friction. The radial travel of the wheels are mechanically linked through a cam and axially reciprocal plunger arrangement that centers the probe at tube diameter transitions. Internal wire bending is minimized and a dynamic seal is provided to facilitate an insertion force at the probe and reduce or eliminate compressive load buckling of the flexible cable carried by the probe. Like the wheel arrangement, radial travel of the seal segments are mechanically linked to provide probe centering.

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19-12-2013 дата публикации

DEVICE FOR INSPECTING A STEAM GENERATOR

Номер: US20130335551A1
Принадлежит: SRA SAVAC

An inspection device for inspecting a steam generator having a first long and flexible video probe intended to be inserted inside the housing of the steam generator and configured to be moveable through a fluid passage orifice defined by a spacer plate and a flow tube, all arranged inside the housing. The first video probe includes at least one ferromagnetic element. The inspection device also includes a second long and flexible probe to be inserted into a flow tube, the second probe including at least one permanent magnet arranged to cooperate with the at least one ferromagnetic element of the first probe so that the first probe can be driven along the exterior surface of a flow tube by the second probe when the second probe is inserted into the flow tube and moved therein, and when the first probe is inserted into the housing of the steam generator and positioned near the exterior surface of the flow tube in which the second probe is inserted. 1. An inspection device for inspecting a steam generator comprising a sealed housing containing a plurality of flow tubes for a first fluid and at least one spacer plate designed to maintain the tubes and having a set of tube passage openings , said sealed housing being designed to receive a second fluid , the inspection device including:a long and flexible first video probe, designed to be inserted into the housing of the steam generator through an opening thereof and configured to be able to be moved through a fluid passage opening delimited by a spacer plate and a flow tube, the first video probe having at least one ferromagnetic element,a long and flexible second probe, designed to be inserted, through an opening of the housing of the steam generator, into a flow tube, the second probe comprising at least one permanent magnet arranged to cooperate with the at least one ferromagnetic element of the first probe so that the second probe can drive the first probe along the outer surface of a flow tube, when the second probe ...

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20-03-2014 дата публикации

Profiling tool for determining material thickness for inspection sites having complex topography

Номер: US20140076053A1
Принадлежит: Atomic Energy of Canada Ltd AECL

A phased array ultrasonic probe may be mounted to a component to be inspected for wall thickness on an apparatus that includes a split ring adapted to be magnetically held in place on the component. In particular, the probe may be mounted to a carriage connected to the split ring in a manner that allows the carriage to rotate around the split ring while the probe is in operation. Between the probe and the component, a transducer shoe defining, by a flexible membrane, a cavity and an aperture. Conveniently, the construction of the flexible membrane allows wall thickness measurements to be acquired in portions of the component that have complex topography, such as welds. The apparatus is installed on an adaptor assembly for inspection of straight section of pipes. This adaptor assembly is not used in absence of straight section. By acquiring data from multiple output pulse transmitted at multiple incidence angles, processing software may conveniently produce an accurate wall thickness map of the area of interest on the component.

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05-01-2017 дата публикации

Method for quantitative estimation of fouling of the spacers plates in a steam generator

Номер: US20170003215A1
Автор: Bruno Renard, Nicolas Paul
Принадлежит: Electricite de France SA

The invention relates to a method for evaluating fouling of the passages of a spacer plate ( 10 ) of a shell-and-tube heat exchanger ( 11 ), wherein said passages ( 12 a, 12 b ) are provided along the tubes ( 11 ) to allow fluid to flow through the spacer plate ( 10 ), wherein, for each of a plurality of at least one passage ( 12 a, 12 b ): at least one measurement of a parameter dependent on fouling or the presence of magnetite is made in the vicinity of the passage, using an eddy current probe; this measurement is used to derive at least one indicator of the fouling of said passage, characterized in that said fouling is evaluated by comparing a set of one or more fouling indicator vectors of dimension of at least two, built from the fouling indicators thus obtained with a plurality of fouling indicator vector sets contained in a database, wherein each of said indicator vector sets is associated with a quantitative descriptor of fouling.

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04-01-2018 дата публикации

INSPECTION DEVICE

Номер: US20180005714A1
Принадлежит: MITSUBISHI HEAVY INDUSTRIES, LTD.

There is provided an inspection device for inspecting an inner surface of a nozzle provided in a reactor vessel. The inspection device includes: a device frame, an inspection unit provided on the device frame, an inspection unit push-out moving mechanism for pushing out and moving the inspection unit to the inner surface of the nozzle, a rotation moving mechanism for rotating and moving the inspection unit, a calibration test unit arranged on the device frame for calibrating the inspection unit; and a calibration test unit forward/backward moving mechanism for moving the calibration test unit forward or backward in the direction along the central axis with regard to a track where the inspection unit makes push-out movement. 1. An inspection device for inspecting a body which is to be inspected , the body being provided in a nuclear power plant ,the inspection device comprising:a device frame installed at the reference position for inspecting the body;an inspection unit provided on the device frame, for inspecting the inspection target portion of the body;an inspection unit push-out moving mechanism for pushing out and moving the inspection unit to the inspection target portion while the device frame is installed at the reference position;a calibration test unit provided on the device frame, for calibrating the inspection unit; anda calibration test unit forward/backward moving mechanism for moving the calibration test unit forward or backward with regard to a track where the inspection unit makes push-out movement in such a state that the inspection unit is installed at the reference position.2. An inspection device for inspecting an inner surface of a nozzle provided in a reactor vessel ,the inspection device comprising:a device frame inserted into inside of the nozzle;an inspection unit provided on the device frame, for inspecting the inner surface of the nozzle;an inspection unit push-out moving mechanism for pushing out and moving the inspection unit to the ...

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15-01-2015 дата публикации

Internal Mechanical Stress Improvement Method for Mitigating Stress Corrosion Cracking in Weld Areas of Nuclear Power Plant Piping

Номер: US20150013425A1
Принадлежит:

Method for mitigating stress corrosion cracking at an internal (i.e., wetted-side) weld area in piping of a nuclear power plant includes the steps of actuating a radially movable tool to produce a radial load against the internal (i.e., normally wetted) surfaces at or near the weld area to create a deep residual compressive stress state at the wetted surface of the weld. The method permits post-process verification by physical measurements of surface distortion. 1. An internal , wetted side , mechanical method for mitigating stress corrosion cracking at an internal weld area in piping in a nuclear power plant comprising the steps ofinserting a tool internally to the piping, the tool having an operating end with a radially movable member;positioning the operating end adjacent the weld area; 'removing the tool to create, when the tool is removed, a deep residual compressive stress state at the weld area.', 'actuating the operating end to move the radially movable member to contact and produce a radial load on the internal surface of the piping near the weld area; and'}2. The method for mitigating stress corrosion cracking at an internal weld area as recited in wherein said actuating step includes mechanically moving a plurality of wedges radially outwardly.3. The method for mitigating stress corrosion cracking at an internal weld area as recited in wherein said actuating step includes supplying fluid to a bladder to radially expand the bladder.4. The method for mitigating stress corrosion cracking at an internal weld area as recited in wherein the radially movable member exerts the radially outward displacement of the pipe at one or more axial locations adjacent the weld area to create a desired magnitude claim 1 , depth and orientation of the residual compressive stress field.5. The method for mitigating stress corrosion cracking at an internal weld area as recited in wherein the weld area is on the inner diameter of a nozzle claim 1 , safe end or pipe. This ...

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17-01-2019 дата публикации

APPARATUS AND METHOD FOR IDENTIFYING CRACKS IN A STRUCTURE USING A MULTI-STAGE CLASSIFIER

Номер: US20190019589A1
Автор: Waite Thomas
Принадлежит:

A method of inspecting a structure for cracks is disclosed. The method includes the steps of moving an inspection vehicle along a pre-determined path through an area to be inspected, the inspection vehicle having a camera apparatus configured to scan the area to be inspected; using the camera apparatus to scan the area to be inspected at a pre-determined distance per second, thereby capturing scan data for analysis; and analyzing the scan data to classify cracks in the structure. 1. A method of inspecting a structure for cracks , comprising the steps of:moving an inspection vehicle along a pre-determined path through an area to be inspected, the inspection vehicle having a camera apparatus configured to scan the area to be inspected;using the camera apparatus to scan the area to be inspected at a pre-determined distance per second, thereby capturing scan data for analysis; andanalyzing the scan data to classify cracks in the structure.2. The method according to claim 1 , wherein the inspection vehicle is autonomous.3. The method according to claim 1 , wherein the inspection vehicle is remote controlled.4. The method according to claim 1 , wherein the step of analyzing includes the steps of:filtering the scan data to generate crack and scratch image frames;registering the crack and scratch image frames to generate a single mosaic image; andperforming shape and segmentation processing to remove small high amplitude disc noise, smooth fragmented cracks, and extract elongated targets that are crack like.5. The method according to claim 4 , wherein the step of filtering includes applying a three-stage filter to the scan image to remove non-uniform illumination claim 4 , separate the scan image into high amplitude scratch and low amplitude crack+grind frames claim 4 , and enhance high special frequency components of cracks.6. The method according to claim 4 , further including the step of generating texture and spatial frequency data for cracks.7. The method according to ...

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04-02-2016 дата публикации

Internal Mechanical Stress Improvement Method for Mitigating Stress Corrosion Cracking in Weld Areas of Nuclear Power Plant Piping

Номер: US20160030990A1
Принадлежит: Individual

Method for mitigating stress corrosion cracking at an internal (i.e., welled-side) weld area in piping of a nuclear power plant includes the steps of actuating a radially movable tool to produce a radial bad against the internal (i.e., normally wetted) surfaces at or near the weld area to create a deep residual compressive stress state at the wetted surface of the weld. The method permits post-process verification by physical measurements of surface distortion.

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01-02-2018 дата публикации

NUCLEAR INSTRUMENTATION SYSTEM AND METHOD FOR LOCATING THE SAME

Номер: US20180033503A1
Принадлежит:

A nuclear instrumentation system and method for locating the same are disclosed. The nuclear instrumentation system includes a source range channel, an intermediate range channel and a power range channel, wherein each channel includes one detector installed around the pressure vessel, the detectors of the power range channel and the intermediate range channel both include several fission chambers, the detectors of the intermediate range channel and power range channel share several fission chambers. Some detectors employ fission chambers, so the Gamma radiation resistance property, anti-noise property and anti-electromagnetic interference property are improved. Sharing fission chambers reduces the number of detectors to be installed, thus relieving the workload of the installation and positioning of the follow-up detector. Further, the present application increases the number of some channels, which increases the redundancy, improves system reliability. 1. A nuclear instrumentation system for surveilling reactor core parameters of the pressure vessel , including a source range channel , an intermediate range channel and a power range channel , wherein each channel includes one detector installed around the pressure vessel , the detectors of the power range channel and the intermediate range channel both include several fission chambers , the detectors of the intermediate range channel and the power range channel share several fission chambers2. The nuclear instrumentation system according to claim 1 , wherein the detector of the power range channel includes four fission chambers connected in turn claim 1 , wherein claim 1 , the four fission chambers are homogeneously distributed at both sides of a core plane at ½ height of the core along an axial direction of the pressure vessel claim 1 , the detector of the intermediate range channel shares both two middle fission chambers of the detector of the power range channel.3. The nuclear instrumentation system according ...

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19-02-2015 дата публикации

SYSTEMS, APPARATUSES AND METHODS OF GRIPPING, CUTTING AND REMOVING OBJECTS

Номер: US20150047487A1
Принадлежит:

A system includes a first platform movably mounted to a first rail assembly, a second rail assembly coupled to and supported by the first platform, and a second platform movably mounted to the second rail assembly. At least one articulating arm is coupled to the second platform, and a gripping and cutting apparatus is coupled to and supported by the at least one articulating arm. An apparatus includes first and second gripping mechanisms each configured for selective actuation between positions for gripping and releasing an object, and a cutting mechanism positioned generally between the first and second gripping mechanisms, and configured to cut the object when gripped on either side by the gripping mechanisms. The system and apparatus can be used to remove feeder pipes of a nuclear reactor power plant. 1. A system , comprising:a first rail assembly extending generally parallel to a first direction;a first platform movably mounted to the first rail assembly;a second rail assembly coupled to and supported by the first platform, and extending generally parallel to a second direction;a second platform movably mounted to the second rail assembly;at least one articulating arm coupled to the second platform; anda gripping and cutting apparatus coupled to and supported by the at least one articulating arm.2. The system of claim 1 , wherein the at least one articulating arm is pivotably coupled to the second platform at a first yaw joint.3. The system of claim 2 , wherein the at least one articulating arm is selectively pivotable about an axis that is generally parallel to the second direction.4. The system of claim 3 , wherein the gripping and cutting apparatus is pivotably coupled to the at least one articulating arm at a second yaw joint.5. The system of claim 4 , wherein the gripping and cutting apparatus is selectively pivotable about an axis that is generally parallel to the second direction.6. The system of claim 5 , comprising a first drive mechanism configured to ...

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19-02-2015 дата публикации

Laser Welding Apparatus, Preventive Maintenance Method for Reactor Internal of Nuclear Power Plant, and Laser Cutting Apparatus

Номер: US20150048059A1
Принадлежит:

The laser welding apparatus includes a welding head and a welding head scanning apparatus. A collimate lens installed on a head body of the welding head is arranged opposite to an end face of optical fibers. The welding head includes only the collimate lens as a lens and the length is shortened. A laser generated by a laser oscillator is introduced into the optical fiber, enters the collimate lens, and then is converted to a parallel beam by the collimate lens. The laser of a parallel beam is irradiated on a surface a welding portion of the welding object through a laser path and the surface of the welding portion is melted. Metallic powder is jetted from powder feed paths formed in a head body to the melted portion and build-up welding is performed on the surface of the welding portion. 1. A laser welding apparatus comprising:a welding head including a head body, and a collimate lens opposite to an end face of an optical fiber connected to the head body and installed in the head body; anda welding head scanning apparatus of scanning the welding head,wherein a laser path of introducing a laser emitted from the optical fiber and passing through the collimate lens is formed in the head body;wherein the welding head includes only the collimate lens as a lens; andwherein a laser outlet of the laser path is formed in an end portion of the head body.2. The laser welding apparatus according to claim 1 ,wherein a powder feed path of introducing metallic powder which is a filler metal is formed in the head body; andwherein an injection outlet of the powder feed path is formed in the end portion of the head body.3. A prevention maintenance method of a reactor internal of a nuclear power plant claim 1 , comprising steps of:using a laser welding apparatus comprising a welding head including a head body, and a collimate lens opposite to an end face of an optical fiber connected to the head body and installed in the head body; and a welding head scanning apparatus of scanning the ...

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14-02-2019 дата публикации

EDDY CURRENT INSPECTION PROBE

Номер: US20190049410A1
Автор: Wekell William Oren
Принадлежит:

A number of embodiments of inventive eddy current probes for non-destructive inspection of electrically conductive tubes are described. These include a bearing-centered probe, a spring loaded wheel-centered probe, a multi-part probe for curved tube inspection having limited excursion ball joints connecting the probe parts, and a 3D printed probe including features that are incapable of being manufactured through conventional casting or machining processes. 1. An eddy current probe for insertion into and non-destructive testing of an electrically conductive cylindrical tube having an axis wherein the tube includes straight and curved portions , the eddy current probe comprising:a sensor portion having a sensor portion axis and an axial center;a front sensor guide comprising first centering feet; anda rear sensor guide comprising second centering feet,said sensor portion being attached to said front sensor guide with a first limited travel ball joint,said sensor portion being attached to said rear sensor guide with a second limited travel ball joint,wherein location of said limited travel ball joints with respect to said first and second centering feet and with further respect to said axial center of said sensor portion being configured to position said sensor portion so as to align said sensor portion axis with the axis of the tube inner walls within both straight and curved portions of the tube under test.2. The eddy current probe of claim 1 , wherein said sensor portion comprises a coil bobbin and coil windings.3. The eddy current probe of claim 1 , wherein said sensor portion comprises an array of coils.4. The eddy current probe of claim 1 , wherein said sensor portion comprises a hall effect or magneto-resistive magnetic field sensor.5. The eddy current probe of claim 1 , wherein said sensor portion comprises an excitation coil and either a sensing coil claim 1 , a sensing coil array claim 1 , a hall effect or magneto-resistive electromagnetic field sensor or an ...

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23-02-2017 дата публикации

METHOD OF PROVIDING AND EVALUATING A MID-WALL REPAIR

Номер: US20170053717A1
Принадлежит: AZZ WSI LLC

A method of repairing and inspecting a first nozzle penetrating a closed vessel. The method includes removing a portion of the first nozzle, and forming a weld between a replacement nozzle and a surface of the mid-wall of the vessel. The method further includes evaluating the integrity of the weld at the mid-wall of the vessel. 1. A method of repairing and inspecting a first nozzle penetrating a closed vessel , comprising:removing a portion of the first nozzle;forming a weld between a replacement nozzle and a surface of the mid-wall of the vessel; andevaluating the integrity of the weld at the mid-wall of the vessel.2. The method according to wherein evaluating comprises performance of a liquid penetrant test of the weld.3. The method according to claim 1 , wherein evaluating comprises comparing a characteristic of the weld to a characteristic of at least one of a known defective weld and a known defect-free weld.4. The method according to claim 1 , wherein evaluating comprises comparing a characteristic of the weld obtained through ultrasonic inspection.5. The method according to claim 4 , wherein evaluating comprises comparing at least one of an echodynamic signature including response amplitude of an ultrasonic signal and time of flight of the ultrasonic signal obtained by an ultrasonic inspection of the weld. This patent application is a divisional of U.S. patent application Ser. No. 11/091,767, filed Mar. 29, 2005, the contents of which are incorporated by reference herein in their entirety.The present invention is directed to a method of providing a mid-wall repair, as well as a method of evaluating the mid-wall repair.In pressurized water (PWR) and boiling water (BWR) nuclear reactors, multiple penetrations are provided in a pressure vessel or piping. The penetrations consist of sleeves and/or nozzles that extend from the exterior of the pressure vessel through openings in a low alloy or carbon steel vessel wall and a nickel-chromium-iron (Ni—Cr—Fe) or ...

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23-02-2017 дата публикации

CLOSED VESSEL HAVING A MID-WALL REPAIR

Номер: US20170053718A1
Принадлежит: AZZ WSI LLC

A closed vessel having a mid-wall. The mid wall is disposed between an interior wall and an exterior wall of the vessel. A first nozzle extends from a first portion of the mid-wall to the interior of the vessel. A second nozzle extends from a second portion of the mid-wall to the exterior of the vessel. A weld is disposed between the second portion of the mid-wall and the second nozzle. 1. A closed vessel , comprising:a mid-wall disposed between an interior wall and an exterior wall of the vessel; a first nozzle extending from a first portion of the mid-wall to the interior of the vessel;a second nozzle extending from a second portion of the mid-wall to the exterior of the vessel; anda weld disposed between the second portion of the mid-wall and the second nozzle.2. The closed vessel according to claim 1 , wherein the weld comprises a plurality of weld layers.3. The closed vessel according to claim 2 , wherein the plurality of weld layers comprises at least three weld layers.4. The closed vessel according to claim 1 , wherein the weld has a thickness about equal to a thickness of a replacement nozzle.5. The closed vessel according to claim 1 , further comprising:a clad disposed on the interior surface of the vessel; anda connection disposed between the clad or combination of clad and vessel and the first nozzle.6. The closed vessel according to claim 5 , wherein the connection comprises a weld. This patent application is a divisional of U.S. patent application Serial No. 11/091,767, filed Mar. 29, 2005, the contents of which are incorporated by reference herein in their entirety.The present invention is directed to a method of providing a mid-wall repair, as well as a method of evaluating the mid-wall repair.In pressurized water (PWR) and boiling water (BWR) nuclear reactors, multiple penetrations are provided in a pressure vessel or piping. The penetrations consist of sleeves and/or nozzles that extend from the exterior of the pressure vessel through openings in a ...

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20-02-2020 дата публикации

Internal Mechanical Stress Improvement Method for Mitigating Stress Corrosion Cracking in Weld Areas of Nuclear Power Plant Piping

Номер: US20200055106A1
Принадлежит: MPR Associates, Inc.

Method for mitigating stress corrosion cracking at an internal (i.e., wetted-side) weld area in piping of a nuclear power plant includes the steps of actuating a radially movable tool to produce a radial bad against the internal (i.e., normally wetted) surfaces at or near the weld area to create a deep residual compressive stress state at the wetted surface of the weld. The method permits post-process verification by physical measurements of surface distortion. 1. An internal , wetted side , mechanical method for mitigating stress corrosion cracking at an internal wetted weld area in piping in a nuclear power plant , the piping having an internal wetted surface , said method comprising the steps ofinserting a tool internally to the piping, the tool having an operating end with a radially movable member;positioning the operating end adjacent the weld area;actuating the operating end to move the radially movable member to produce a radial load on the internal wetted surface of the piping at the weld area to create a compressive stress state beneath the internal wetted surface at a depth greater than 1 mm by imposing a deformation layer beyond plastic yield strength, greater than 2% strain; andremoving the tool to leave the residual compressive stress state at the weld area when the tool is removed.2. The method for mitigating stress corrosion cracking at an internal weld area as recited in wherein said actuating step includes mechanically moving a plurality of wedges radially outwardly.3. The method for mitigating stress corrosion cracking at an internal weld area as recited in wherein said actuating step includes supplying fluid to a bladder to radially expand the bladder.4. The method for mitigating stress corrosion cracking at an internal weld area as recited in wherein the radially movable member exerts the radially outward displacement of the pipe at one or more axial locations adjacent the weld area to create a desired magnitude claim 1 , depth and orientation ...

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28-03-2019 дата публикации

SYSTEM FOR SIMULTANEOUS MULTI-TUBE INSPECTION OF VERTICAL TUBE BUNDLES

Номер: US20190094514A1
Автор: Tripathy Kishlay
Принадлежит: Clearwater Downstream Services, LLC

A multi-tube inspection system with a reel having a plurality of cameras is placed in the upper header. Each camera is attached to its own lead line and has a light source. An inspector, located in the upper header, aligns each camera with a tube and then operates the reel to simultaneously lower the cameras through their respective tube. As the cameras pass through the tubes, they capture a video image of the interior length of the tube. The video image is stored and relayed to a control center where additional inspectors can review the video image of the interior of the tube. Each video is identified and tied back to the tube in a data base. If a defect is identified, the tube can be taken out of service (blocked off) or scheduled for cleaning. Once cleaned, the tube is then reinspected. 1. A system for a simultaneously inspecting multiple tubes in a tube bundle , the system comprising:a stand with legs; a drum and a camera control unit;the drum has a plurality of reels, each reel having a camera and light source attached to a lead line secured to the reel; anda guide jig with the lead lines passing through the guide jig.2. The system of further comprising:a drive motor engagable with the drum;wherein operation of the drive motor causes rotation of the drum.3. The system of further comprising:a battery capable of providing power to the plurality of cameras, the light sources, the drive motor and the camera control unit.4. The system of further comprising a control center having a video display device.5. The system of further comprising the camera control unit having a DVR storage and a wireless connection to the control center.6. The system of further comprising the camera control unit having a DVR storage and a wireless connection to the control center.7. The system of further comprising the stand and the drum being located in an upper header of a reactor above a vertically oriented tube bundle.8. The system of further comprising the control center being located ...

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04-04-2019 дата публикации

SYSTEMS AND METHODS FOR ASSAYING AN OBJECT

Номер: US20190103196A1
Автор: Horn Dag, Stoev Krassimir
Принадлежит:

A method for assaying a wall of a pressure tube for a nuclear reactor is disclosed. The wall has a matrix material and deuterium nuclei in the matrix material. The method includes: (a) transmitting gamma rays into the matrix material to induce photodisintegration of at least some of the deuterium nuclei, whereby reaction particles of the nuclei are emitted from the wall; (b) detecting at least some of the reaction particles emitted in step (a) using a particle detector; and (c) generating particle signals in response to detecting the particles in step (b). 1. A method for assaying a wall of a pressure tube for a nuclear reactor , the wall having a matrix material and deuterium nuclei in the matrix material , the method comprising:a) transmitting gamma rays into the matrix material to induce photodisintegration of at least some of the deuterium nuclei, whereby reaction particles of the nuclei are emitted from the wall;b) detecting at least some of the reaction particles emitted in step (a) using a particle detector; andc) generating particle signals in response to detecting the particles in step (b).2. The method of claim 1 , further comprising determining an attribute of the wall based at least in part on the particle signals.3. The method of claim 2 , wherein the attribute comprises a concentration of the deuterium nuclei in the matrix material.4. The method of claim 2 , wherein the particle signals indicate a number of the reaction particles detected in step (b).5. The method of claim 4 , wherein determining the attribute comprises comparing the number of the reaction particles detected in step (b) with a predetermined reference value.6. The method of claim 1 , wherein the matrix material comprises a zirconium alloy.7. The method of claim 6 , wherein the zirconium alloy comprises at least one of Zircaloy-2 and Zr-2.5Nb.8. The method of claim 1 , further comprising claim 1 , prior to step (a) claim 1 , subjecting an n-gamma radiator to a neutron flux to induce an n ...

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29-04-2021 дата публикации

METHOD AND DEVICE FOR REPLACING SLEEVES LINING NUCLEAR REACTOR PRESSURE VESSEL TUBES

Номер: US20210125739A1
Автор: MARKHAM Wade, Melcher Ryan
Принадлежит:

A method for restraining a sleeve lining a tube passing through a nuclear reactor pressure vessel is provided. The method includes attaching in situ a radial protrusion on an external surface of the sleeve; and attaching a collar to an end of the tube and coupling the radial protrusion with the collar to retain the thermal sleeve in position. 1. A method for replacing a sleeve lining a tube passing through a nuclear reactor pressure vessel , the sleeve having an end including a radially enlarged end portion configured for resting on a support section of the tube for retaining the sleeve in the tube , the method comprising:removing the sleeve from the tube;providing a new sleeve with a radially variable end configured for being moved between a radially contracted configuration and a radially expanded configuration; andinstalling the new sleeve in the tube such that the radially variable end is received by the support section and the radially variable end retains the new sleeve in the tube, the radially variable end being in the radially contracted configuration during installation and being in the radially expanded configuration after the new sleeve is installed in the tube.2. The method as recited in wherein the installing of the new sleeve includes inserting the radially variable end in the radially contracted configuration in a first end of the tube claim 1 , the radially variable end being in the radially expanded configuration in a second end of the tube after installation.3. The method as recited in wherein the first end of the tube is a lower end of the tube and the second end of the tube is an upper end of the tube.4. The method as recited in wherein the radially variable end includes a plurality of circumferentially spaced segments that are flexible radially inward and radially outward.5. The method as recited in wherein each of the circumferentially spaced segments includes a radially outward protrusion resting on the support section after the new sleeve is ...

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14-05-2015 дата публикации

CONSTRUCTION METHOD, TUBULAR MEMBER, AND NUCLEAR POWER PLANT

Номер: US20150131767A1
Принадлежит: MITSUBISHI HEAVY INDUSTRIES, LTD.

A construction method of a pipeline that forms a pipeline by joining tubular members to each other by butt welding, includes: a tubular member preparation step for preparing a tubular member having a smooth length of an outer surface along an axial direction from a joined end, which is set based on conditions of ultrasonic inspection of a welded portion, which are determined by usage conditions of the pipeline; a tubular member welding step for welding together prepared tubular members; and a welded portion inspection step for inspecting a welded portion by ultrasonic inspection. 1. A construction method of a pipeline that forms a pipeline of a nuclear power plant by joining tubular members to each other by butt welding , comprising:a tubular member preparation step for preparing a tubular member having a smooth length of an outer surface along an axial direction from a joined end, which is set based on a flaw inspection area, a thickness of the tubular member, an ultrasonic wave incidence angle, a probe play, a probe individual difference, and a scanning allowance of a welded portion, which are determined by usage conditions of said pipeline;a tubular member welding step for welding together prepared tubular members; anda welded portion inspection step for inspecting a welded portion by ultrasonic inspection.2. A construction method of a pipeline according to claim 1 , wherein claim 1 , in said tubular member preparation step there is provided a tubular member having said outer surface smooth length claim 1 , and an inner surface smooth length along an axial direction from a joined end claim 1 , which is set based on a flaw inspection area claim 1 , a thickness of the tubular member claim 1 , an ultrasonic wave incidence angle claim 1 , and an ultrasonic wave spread width of a welded portion claim 1 , which are determined by usage conditions of said pipeline. This application is a divisional of U.S. application Ser. No. 13/344,043 filed on Jan. 5, 2012, which is ...

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16-04-2020 дата публикации

REACTOR PRESSURE VESSEL INCLUDING PIPE RESTRAINT DEVICE, AND/OR PIPE RESTRAINT DEVICE

Номер: US20200116286A1
Принадлежит: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC

A reactor pressure vessel includes a reactor pressure vessel body, a nozzle structure connected to the reactor pressure vessel body, a conduit structure connected to the nozzle structure, and a restraint device attached around a portion of the conduit structure. The restraint device includes collar parts that have cross sections corresponding to respective segments of a periphery of the portion of the conduit structure, brackets attached to the nozzle structure, and rods connecting the brackets to the collar parts. The collar parts are connected end-to-end to each other such that a cross section of the collar parts connected to each other corresponds to the periphery of the portion of the conduit structure. The collar parts are pinned to each other. The brackets spaced apart from each other around a periphery of the nozzle structure. 118.-. (canceled)19. A method of attaching a restraint device to a conduit structure connected to a nozzle structure that includes brackets on an outer surface of the nozzle structure , the method comprising:inserting a first end of rods into the brackets such that a remaining part of each of the rods extends from the brackets over a portion of the conduit structure; the collar parts each including a side that defines a threaded hole,', 'the connecting collar parts to the rods including inserting a second end of each of the rods into a corresponding threaded hole among the threaded holes defined by the collar parts; and, 'connecting collar parts to the rods,'}pinning the collar parts to each other end-to-end such that the collar parts pinned to each other wrap around the portion of the conduit structure.20. The method of claim 19 , further comprising:inserting one or more Belleville washers between the portion of the conduit structure and at least one of the collar parts.21. The method of claim 19 , further comprising:inserting engineered-crush material between the portion of the conduit structure and at least one of the collar parts.22 ...

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19-05-2016 дата публикации

Excavation and Weld Repair Methodology for Pressurized Water Reactor Piping and Vessel Nozzles

Номер: US20160141057A1
Принадлежит:

The invention is an innovative design/repair methodology for PWR piping nozzles and vessel nozzles that are attached to the piping/vessel base material with a full penetration weld joint geometry. The development of a robust repair methodology for nozzles of this configuration is necessary due to plant aging, potential material degradation in the original materials of construction, potential increased nondestructive examination requirements, and PWSCC phenomena in the susceptible original materials of construction. The purpose/objective of the repair methodology is to provide a means of partially replacing the existing pressure boundary susceptible materials with PWSCC-resistant materials to facilitate the long-term repair life of the plant. The invention may be applied to a plurality of nozzle, piping, and vessel sizes with a full penetration weld joint. 1. A method of repairing an original weld connecting a base material to an original nozzle , comprising:removing a portion of the base material, the original nozzle, and the original weld to create a counterbore having a base surface and a side all such that at least some of the original nozzle and the original weld remain creating an original nozzle remnant and an original weld remnant;providing a replacement nozzle having a bottom surface;placing said replacement nozzle within the counterbore such that said bottom surface contacts said counterbore base surface and a void is created between said replacement nozzle and said counterbore side wall; anddepositing a replacement weld in said void to attach said replacement nozzle to said counterbore side wherein said replacement nozzle and said replacement weld are formed of materials resistant to primary water stress corrosion cracking.2. The method of claim 1 , wherein said depositing includes attaching said replacement nozzle to the base material.3. The method of claim 1 , wherein said depositing further includes attaching said replacement nozzle to the original weld ...

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14-06-2018 дата публикации

SYSTEMS AND METHODS FOR NUCLEAR REACTOR DRY TUBE ASSEMBLY REMOVAL AND INSTALLATION

Номер: US20180161944A1
Принадлежит:

Dry tube tooling systems can manipulate dry tubes in reactors without removing all fuel next to the tubes, saving considerable outage time and allowing fresh detectors and instrumentation to be installed throughout fuel shuffling. Bodies of the tooling fits through a top guide and secure to the same without completely surrounding the dry tube or requiring all nearby fuel to be removed. The tooling includes a retainer that moves to secure to the dry tube and vertically and/or horizontally move the same. The retainer can release or install the dry tube in a fixed core location through such movement. Dry tubes can thus be installed and/or removed by operating the tooling from a bridge or crane above the reactor. The movement of the retainer can be achieved by power or signals from the operators to move and grasp the dry tube in a desired manner. 1. A tool system for handling a dry tube in a nuclear reactor including a plurality of fuel assemblies arranged under a top guide having a grid shape inside the nuclear reactor , the system comprising:a body shaped to fit through a single opening in the grid and secure to the top guide; anda moveable retainer shaped to selectively secure to the dry tube from the single opening so as to move the dry tube without intersecting one of the fuel assemblies directly adjacent to the dry tube.2. The tool of claim 1 , further comprising:a plurality of wings attached to the body and shaped to fit around two separate sides of the grid at a top end of the top guide.3. The tool of claim 2 , wherein each of the wings extend at a 90-degree angle from each other.4. The tool of claim 1 , wherein the moveable retainer is a grasping fork configured to clamp around the dry tube.5. The tool of claim 4 , wherein the grasping fork is configured to move transversely outward from the body and vertically downward so as to unseat the dry tube from the top guide.6. The tool of claim 1 , wherein the moveable retainer is remotely powered.7. The tool of claim ...

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06-06-2019 дата публикации

Heat Pipe Assembly of Nuclear Apparatus Having Fiber Optical Temperature Detection System

Номер: US20190172597A1
Принадлежит: Westinghouse Electric Co LLC

A heat pipe assembly of a nuclear apparatus includes a number of elongated heat pipes and a detection system having one or more fiber optic cable assemblies that are elongated and are wrapped in a helical fashion along an exterior surface of one or more of the heat pipes. The detection system further includes an optical signal generator that supplies to each, fiber optic assembly an optical signal and additionally includes a sensor that detects a number of reflections of the optical signal and generates an output. The output is usable by an instrumentation and control system to determine a number of temperatures along one or more of the heat tubes by detecting a temperature at each of a plurality of locations along each fiber optic cable assembly.

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27-06-2019 дата публикации

ULTRASOUND INSPECTION

Номер: US20190195829A1
Принадлежит:

A device and method for performing ultra-sound scanning of a substantially cylindrical object. The device comprises a cuff adapted to fit around a circumference of the object, an ultrasound probe mounted about the inner circumference of the cuff and positioned to scan the circumference of the object, and one or more data connections providing control information for the ultrasound probe and receiving scanning data from the ultrasound probe. The probe includes one or more sensors to determine its orientation or location, and this data is used to control the operation of the device and to process data from the array. 1. A method for performing ultrasound scanning of a conduit , comprising:providing an ultrasound array having a plurality of ultrasound elements arrayed about the circumference of the conduit and at least one sensor providing one or more of the acceleration of the array and position of the array;positioning the ultrasound array to project ultrasound signals toward an external surface of the conduit at a first point along the longitudinal axis of the conduit;performing a full-matrix-capture scan of the first point along the longitudinal axis of the conduit, comprising:transmitting an ultrasound signal from a first ultrasound element in the ultrasound array;sensing and recording ultrasound signals received by each other ultrasound element in the ultrasound array; andrepeating the steps of transmitting, sensing and recording, wherein the step of transmitting is performed in turn by each ultrasound element in the ultrasound array other than the first ultrasound element;repositioning the ultrasound array at a second point a along the longitudinal axis of the conduit;performing a full-matrix-capture scan of the second point along the longitudinal axis of the conduit;using data from the at least one sensor to correlate the scan at the first point and the scan at the second point to each other; andrepeating the steps of repositioning and performing a full-matrix- ...

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06-08-2015 дата публикации

APPARATUS AND METHOD TO REMOTELY INSPECT PIPING AND PIPING ATTACHMENT WELDS

Номер: US20150221401A1
Принадлежит: WESTINGHOUSE ELECTRIC COMPANY LLC

An apparatus and method to remotely perform automated piping and piping attachment weld inspections. The apparatus has two spaced positioning arms that rotate out from one side of a frame structure and a kicker arm that rotates out from an opposite side of the frame structure at a location between the two positioning arms. The positioning arms and the kicker arm wedge the frame structure between an object to be scanned and an opposing structure. A scanning subassembly supported on the frame structure is configured to pivot and move in an appropriate direction and to pilot a transducer around the surface of the object to be scanned. 1. An automated inspection assembly that includes a number of subassemblies comprising:a frame subassembly, having a first side and a second side having a length and width with the width substantially larger than a thickness of the frame subassembly between the first side and the second side, and the length having a first end and a second end along a longitudinal dimension of the length, the frame subassembly being configured to form the main support structure for the automated inspection assembly;a positioning arms subassembly, coupled to the frame subassembly, including a support arm remotely operable to extend out from or retract toward the first side of the frame subassembly;a kicker arm remotely operable to extend out from or retract toward the second side of the frame subassembly, the support arm and the kicker arm in an extended position being operable to wedge the frame subassembly between a member to be inspected and a surface opposed to the member to be inspected;a scanning subassembly supported from the frame subassembly and configured to scan at least a portion of the member; andwherein at least one of the kicker arm and the support arm is operable to move hydraulically.2. The automated inspection assembly of including an orientation pivot subassembly including a rotational pivot joint coupling the orientation pivot ...

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05-08-2021 дата публикации

METHOD OF DETECTING AN EXISTENCE OF A LOOSE PART IN A STEAM GENERATOR OF A NUCLEAR POWER PLANT

Номер: US20210241931A1
Автор: LE QUI V.
Принадлежит: WESTINGHOUSE ELECTRIC COMPANY LLC

A plurality of signal anomalies are identified in a number of tubes in a steam generator. Since the geometry of the steam generator is known, the location of each signal anomaly along each tube is converted into a location within the interior of the steam generator. If a plurality of signal anomalies are at locations within the steam generator that are within a predetermined proximity of one another, such a spatial confluence of signal anomalies is determined to correspond with a loose part situated within the steam generator. Additional methodologies can be employed to confirm the existence of the loose part. Historic tube sheet transition signal data can be retrieved and subtracted from present signals in order to enable the system to ignore the relatively strong eddy current sensor signal of a tube sheet which would mask the relatively weak signal from a loose part at the tube sheet transition. 1. A method of non-destructively detecting an existence of a loose part within a steam generator of a nuclear power plant , the steam generator having a plurality of tubes within an interior thereof , the method comprising:identifying in a first eddy current signal a first signal anomaly at a first tube position along a first tube from among the plurality of tubes, and converting the first tube position along the first tube into a three-dimensional first generator location within the interior of the steam generator;identifying in a second eddy current signal a second signal anomaly at a second tube position along a second tube from among the plurality of tubes different from the first tube, and converting the second tube position along the second tube into a three-dimensional second generator location within the interior of the steam generator;making a determination that the first generator location and the second generator location are within a predetermined proximity of one another; andresponsive to the determination, determining that a loose part exists in the vicinity ...

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20-08-2015 дата публикации

Ultrasonic phased array transducer for the nde inspection of the jet pump riser welds and welded attachments

Номер: US20150233869A1
Принадлежит: Westinghouse Electric Co LLC

An ultrasonic phased array transducer assembly having a single housing in which a plurality of phased array transducer subassemblies are mounted at a skewed angle relative to a leading face of the housing and to each other, with each transducer mounted on composite wedge(s) at different orientations within the housing.

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20-11-2014 дата публикации

Apparatus and method for inspecting pipelines

Номер: US20140338472A1
Автор: Hyun Young Chang

Apparatus and method for inspecting pipeline are provided. The pipeline inspecting apparatus moving along an external circumferential surface of a pipeline to inspect the pipeline, includes: a main frame having an arc shape having an opened portion to surround the pipeline; a main movement unit that is movably installed on the main frame, wherein the main movement unit is movably installed along a length direction of the pipeline while being in contact with the external circumferential surface of the pipeline; an auxiliary frame that has an arc shape having an opened portion to surround the pipeline and is separated from the main frame to face the main frame; an auxiliary frame adjusting unit that movably connects the auxiliary frame to the main movement unit in a circumferential direction of the pipeline; and a sensor adjusting unit that is fixed to the auxiliary frame, wherein a sensor for inspecting a state of the pipeline is installed.

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28-09-2017 дата публикации

ASSEMBLY FOR ACTING ON THE OUTER SURFACE OF A TUBE, AND CORRESPONDING METHOD

Номер: US20170278587A1
Принадлежит:

An assembly for acting on the outer surface of a tube, and corresponding method are provided. The assembly includes a carrier; at least one inspection or maintenance tool; the carrier includes at least one rolling body; an actuator. The carrier further includes a device for connecting the carrier to the tube, arranged so that the tube absorbs at least 50% of the weight of the carrier and the tool. 117-. (canceled)18. An assembly for acting on an outer surface of a tube , the assembly comprising:a carrier movable along the tube;at least one inspection or maintenance tool, connected to the carrier; at least one rolling body, placed in contact with the outer surface of the tube;', 'an actuator, arranged to rotate the rolling body relative to the tube, so as to propel the carrier along the tube by cooperation between the rolling body and the outer surface of the tube; and', 'a connector for connecting the carrier to the tube, arranged so that the tube absorbs at least 50% of the weight of the carrier and the tool., 'the carrier comprising19. The assembly according to claim 18 , wherein the carrier comprises a chassis to which the at least one rolling body is connected claim 18 , the connector comprising at least one roller connected to the chassis claim 18 , arranged so as to pinch the tube between the at least one roller and the at least one rolling body with a predetermined force.20. The assembly according to claim 19 , wherein the at least one rolling body has a nonslip coating claim 19 , the nonslip coating claim 19 , the predetermined force and a maximum motor torque that is transmittable by the actuator to the at least one rolling body being chosen so that the carrier and the tool can be kept immobile around a vertical tube segment.21. The assembly according to claim 19 , wherein the connector includes at least one gripper bearing at least one of the rollers claim 19 , and a connection of the gripper to the chassis arranged so that the gripper is movable between ...

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25-11-2021 дата публикации

OPTICAL FIBER LASER INDUCED BREAKDOWN SPECTROSCOPY DETECTION DEVICE AND METHOD

Номер: US20210364434A1
Принадлежит:

An optical fiber laser induced breakdown spectroscopy detection device and a detection method are provided. The device comprises an optical fiber LIBS detector and a master control detection system. The master control detection system is installed in the master control room of a nuclear power plant, and the optical fiber LIBS detector is configured to perform detection in a pipeline. The master control detection system and the optical fiber LIBS detector are connected to each other via the transmission optical fiber and the control signal line. The remote on-line detection of the positioning and fixed point of the designated area of the inner wall of the main pipeline of the nuclear power plant can be detected on line in the master control room of the nuclear power plant. 1. An optical fiber laser induced breakdown spectroscopy detection device , comprising:an optical fiber LIBS detector configured to enter a pipeline and perform detection in the pipeline; anda master control detection system installed in a master control room of a nuclear power plant,wherein the optical fiber LIBS detector and the master control detection system are connected to each other via a transmission optical fiber and a control signal line, the optical fiber LIBS detector comprises a lifting platform installed with a rotational mechanism thereon, a telescopic mechanism is connected to the rotational mechanism, and an optical fiber LIBS probe is installed at an end of the telescopic mechanism;a lifting driving mechanism is provided at a bottom of the lifting platform, and at least one moving component is installed at a bottom of the lifting driving mechanism; andthe optical fiber LIBS probe is connected to one end of the transmission optical fiber.2. The optical fiber laser induced breakdown spectroscopy detection device according to claim 1 , wherein a radial distance sensor claim 1 , an illuminating lamp and a camera are installed at a joint of the telescopic mechanism and the optical ...

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12-11-2015 дата публикации

Water jet peening device

Номер: US20150321299A1
Принадлежит: Mitsubishi Heavy Industries Ltd

The water jet peening device of the present invention is provided with: a swiveling mechanism for swiveling a spray nozzle in the horizontal direction centered on a positioning member that is positioned at the upper end of an instrumentation tube support; a lift mechanism for raising and lowering the spray nozzle in the vertical direction with respect to the positioning member that is positioned at the upper end of the instrumentation tube support; and a rotation mechanism for supporting the spray nozzle so as to be able to rotate centered on a downward-inclined rotation shaft center on the positioning member end of the vertical direction, disposing a spray port aimed toward the side of the rotation shaft center in a direction that is at a slant from the rotation shaft center, and rotating the spray nozzle centered on the rotation shaft center.

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12-11-2015 дата публикации

Nozzle repair method and nuclear reactor vessel

Номер: US20150325319A1
Принадлежит: Mitsubishi Heavy Industries Ltd

A nozzle repair method and a nuclear reactor vessel include: removing a trepanning portion ( 208 ) as a connection portion with respect to an in-core instrumentation cylinder ( 204 ) in a groove-welding portion ( 206 ); removing the in-core instrumentation cylinder ( 204 ) from a semi-spherical portion ( 66 ) as a lower end plate; forming a surface buttered-welding portion ( 210 ) by buttered-welding the surface of the groove-welding portion ( 206 ); forming a welding groove ( 212 ) by grooving the surface buttered-welding portion ( 210 ); inserting a new in-core instrumentation cylinder ( 204 A) provided with a circumferential groove portion ( 204 f ) outside an instrumentation equipment guide passage ( 204 d ) into an attachment hole ( 203 ); and fixing the new in-core instrumentation cylinder ( 204 A) by groove-welding the welding groove ( 212 ). Accordingly, since the nozzle welding area is suppressed to a predetermined range, the workability of the repair is improved.

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10-11-2016 дата публикации

IMPROVED ULTRASOUND INSPECTION

Номер: US20160327520A1
Принадлежит: Ontario Power Generation, Inc.

A device and method for performing ultra-sound scanning of a substantially cylindrical object, the device comprising a cuff adapted to fit around a circumference of the object, an ultrasound probe mounted about the inner circumference of the cuff and positioned to scan the circumference of the object, and one or more data connections providing control information for the ultrasound probe and receiving scanning data from the ultrasound probe. The probe includes one or more sensors to determine its orientation or location, and this data is used to control the operation of the device and to process data from the array. 1. A device for performing ultrasound scanning of a conduit , comprising:a cylindrical cuff adapted to fit around a circumference of the conduit;an ultrasound probe mounted on the cuff and positioned to scan the circumference of the conduit; andone or more sensors mounted on the cuff to determine one of more of the acceleration of the cuff and orientation of the cuff.2. The device of claim 1 , wherein the one or more sensors comprise at least one gyroscope.3. The device of claim 1 , wherein the one or more sensors comprise at least one accelerometer.4. The device of claim 1 , wherein the one or more sensors comprise a gyroscope and an accelerometer operable to determine the orientation and acceleration of the cuff.5. The device of claim 4 , wherein the gyroscope and accelerometer are operable to determine orientation and acceleration in three dimensions.6. A device for performing ultrasound scanning of a conduit claim 4 , comprising:a cylindrical cuff adapted to fit around a circumference of the conduit;an ultrasound probe mounted on the cuff and positioned to scan the circumference of the conduit; andat least one indicator for alerting a user of a deficiency in quality of ultrasound probe data.7. The device of claim 1 , further comprising:a seal at either end of the cylindrical cuff for containing fluid in an interior region between the interior surface ...

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26-11-2015 дата публикации

Eddy Current Inspection Probe

Номер: US20150338377A1
Принадлежит:

A device and method of eddy current based nondestructive testing of tubular structures made of electrically conductive materials is disclosed. The probe includes means for producing an electromagnetic field for inducing an eddy current in a device under test, means for sensing eddy current signals in the device under test, and an analog to digital converter, wherein the analog to digital converter is conditioned to receive the sensed eddy current signals and to transmit a digital signal related to the eddy current signals. 1. An eddy current probe for nondestructive testing of tubular structures made of electrically conductive materials comprising:a plurality of eddy current drive coils;a plurality of eddy current sensors;a first multiplexer configured to receive signals from said plurality of eddy current sensors;an analog to digital converter configured to receive multiplexed signals from said first multiplexer and to convert said multiplexed signals to a multiplexed digital signal.2. The eddy current probe of claim 1 , further comprising a digital to analog converter configured to receive digital drive signals and convert said digital drive signals an analog signal for driving said drive coils.3. The eddy current probe of claim 2 , further comprising a drive current amplifier claim 2 , a filter and a multiplexer claim 2 , said drive current amplifier configured to amplify said analog signal for driving said drive coils claim 2 , said filter configured to filter said amplified analog signal and said multiplexer configured to direct said analog signal to one of said plurality of eddy current drive coils.4. The eddy current probe of claim 1 , wherein said eddy current sensors are a circumferential array of sensors. This utility application claims the benefit under 35 U.S.C. §119(e) of provisional application Ser. No. 62/000,905 filed on May 20, 2014, and entitled “Eddy Current Probe.”The entire disclosure of the provisional application is incorporated herein by ...

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03-12-2015 дата публикации

METHOD FOR EVALUATING THE CLOGGING OF A HEAT EXCHANGER

Номер: US20150346156A1
Автор: PAUL Nicolas
Принадлежит:

The invention relates to a method for evaluating the clogging of the passages of a tube support plate of a tube heat exchanger, in which an eddy current probe is passed through a tube of said exchanger and a measurement signal is measured with said probe, and, to evaluate the clogging at the downstream edge of a tube support plate: 1. Method for evaluating the clogging of the passages of a tube support plate of a tube heat exchanger , said passages being made along the tubes for a fluid to pass through the tube support plate , in which an eddy current probe is passed through a tube of said exchanger and a measurement signal is measured with said probe according to the environment in which the probe is situated , wherein to evaluate the clogging at the downstream edge of a tube support plate:a lower edge signal corresponding to the probe passing the downstream edge of the tube support plate is determined from the measurement signal,an upper edge signal corresponding to the probe passing the upstream edge of the tube support plate is determined from the measurement signal,the impulse response of the probe is estimated,the lower edge signal is deconvolved by means of said impulse response estimation,the clogging is evaluated by analysing the lower edge signal thus deconvolved.2. Method according to claim 1 , in which the probe acquires at least in part the measurement signal in differential mode.3. Method according to claim 1 , in which the measurement signal is a multifrequency signal composed of at least two signals at different frequencies claim 1 , and the lower edge signal and the upper edge signal result from linear combinations of at least two signals at frequencies different to said measurement signal.4. Method according to claim 3 , in which the linear combination involves at least one complex coefficient optimised to minimise the signal power along the tube outside of the plate zones.5. Method according to claim 4 , in which the impulse response of the probe ...

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15-10-2020 дата публикации

FEEDWATER SPARGER NOZZLE REPAIR ASSEMBLY

Номер: US20200328003A1
Принадлежит: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC

A feedwater sparger repair assembly includes a cover plate having a partial cylindrical shape and having a nozzle opening and a pair of bolt openings extending through the cover plate. A nozzle is attached to the cover plate and surrounds the nozzle opening. A pair of T-bolts extend through a respective one of the pair of bolt openings and each include a shank having a threaded portion extending from an exterior side of the cover plate and a partial cylindrical head portion disposed at an end of the shank on an interior side of the cover plate. A pair of nuts are engaged with the threaded portion of the pair of T-bolts. The feedwater sparger repair assembly is adapted to be mounted to an opening that is cut into a core spray pipe in order to repair/replace a sparger that becomes cracked. 1. A feedwater sparger repair assembly , comprising:a cover plate having a partial cylindrical shape and having a nozzle opening and a pair of bolt openings extending through the cover plate;a nozzle attached to the cover plate and surrounding the nozzle opening;a pair of T-bolts each extending through a respective one of the pair of bolt openings, the T-bolts each including a shank having a threaded portion extending from an exterior side of the cover plate and a partial cylindrical head portion disposed at an end of the shank on an interior side of the cover plate; anda pair of nuts engaged with the threaded portion of the pair of T-bolts.2. The feedwater sparger repair assembly according to claim 1 , wherein the interior side of said cover plate includes an oval shaped protruding portion surrounding the nozzle opening.3. The feedwater sparger repair assembly according to claim 1 , wherein the exterior side of the cover plate includes a protruding region of increased thickness surrounding the pair of bolt openings.4. The feed water sparger repair assembly according to claim 1 , wherein the pair of nuts are crimp nuts.5. The feed water sparger repair assembly according to claim 1 , ...

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08-12-2016 дата публикации

METHOD AND APPARATUS FOR SUPPRESSING FLOW-INDUCED JET PUMP VIBRATION IN A BOILING WATER REACTOR

Номер: US20160358678A1
Принадлежит: CONTINUUM DYNAMICS, INC.

Flow induced vibration (FIV) at the slip joint between a nuclear reactor jet pump mixer and diffuser is suppressed without installing additional parts or altering the jet pump construction. The disclosed method determines a relationship between reactor operating conditions that trigger FIV and the magnitude of a mixer/diffuser transverse contact load. A mathematical analysis on a representative jet pump configuration determines the quantitative relationship between mixer/diffuser cold positions and their positions when the reactor is operating. Thus, a prediction can be made as to whether an installed jet pump will experience FIV, and the mixer and diffuser can be positioned by a mixer adjustment tool when the reactor is cold to provide the necessary operational transverse contact load. Alternatively, a contact load measuring tool directly measures the magnitude and direction of the cold mixer/diffuser transverse contact load to determine if FIV will be suppressed when the reactor is operating. 1. A method of suppressing flow-induced vibration (FIV) in a jet pump for recirculating water in a nuclear reactor , the jet pump including a mixer for accepting recirculated water and a diffuser for accepting the water from the mixer , wherein an end region of the mixer fits within an inlet region of the diffuser at a slip joint with a radial clearance between the mixer and the diffuser , the method comprising:determining a first quantitative relationship between (i) a transverse contact load between the mixer and diffuser at the slip joint, and (ii) a property of the flow through the jet pump related to the onset of FIV;determining a second quantitative relationship between (i) a cold transverse contact load between the mixer and diffuser at the slip joint when the reactor is not operating, and (ii) an operating transverse contact load between the mixer and diffuser at the slip joint under reactor operating conditions; andpositioning the mixer and diffuser relative to each ...

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05-11-2020 дата публикации

ULTRASONIC PHASED ARRAY TRANSDUCER FOR THE NDE INSPECTION OF THE JET PUMP RISER WELDS AND WELDED ATTACHMENTS

Номер: US20200348265A1
Принадлежит: WESTINGHOUSE ELECTRIC COMPANY LLC

An ultrasonic phased array transducer assembly having a single housing in which a plurality of phased array transducer subassemblies are mounted at a skewed angle relative to a leading face of the housing and to each other, with each transducer mounted on composite wedge(s) at different orientations within the housing. 111-. (canceled)12. A phased array transducer assembly configured to characterize a structure of a test piece , the phased array transducer assembly comprising a housing comprising an internal cavity , a wedge positioned within the internal cavity , and a phased array subassembly mounted on the wedge.13. The phased array transducer assembly of claim 12 , wherein a face of the housing is positioned relative to the test piece claim 12 , and wherein the phased array subassembly is oriented at a first angle relative to the face of the housing.14. The phased array transducer assembly of claim 13 , wherein the face of the housing is contoured claim 13 , and wherein the contour of the face is determined based claim 13 , at least in part claim 13 , on a corresponding feature of the test piece.15. The phased array transducer assembly of claim 14 , wherein the test piece comprises a pipe of a boiling water reactor claim 14 , wherein the contour comprises a concave surface claim 14 , and wherein the corresponding feature of the test piece comprises a convex surface of the pipe.16. The phased array transducer assembly of claim 13 , wherein the housing further comprises a shoulder mount claim 13 , and wherein the shoulder mount is configured to engage a gimbal configured to reposition the face of the housing relative to the test piece.17. The phased array transducer assembly of claim 13 , further comprising a second wedge positioned within the internal cavity of the housing and a second phased array subassembly mounted to the second wedge claim 13 , wherein the second phased array subassembly is oriented at a second angle relative to the face of the housing claim ...

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05-11-2020 дата публикации

Apparatus and method to remotely inspect piping and piping attachment welds

Номер: US20200350087A1
Принадлежит: Westinghouse Electric Co LLC

An apparatus and method to remotely perform automated piping and piping attachment weld inspections. The apparatus has two spaced positioning arms that rotate out from one side of a frame structure and a kicker arm that rotates out from an opposite side of the frame structure at a location between the two positioning arms. The positioning arms and the kicker arm wedge the frame structure between an object to be scanned and an opposing structure. A scanning subassembly supported on the frame structure is configured to pivot and move in an appropriate direction and to pilot a transducer around the surface of the object to be scanned.

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26-11-2020 дата публикации

SYSTEMS AND METHODS FOR NUCLEAR REACTOR DRY TUBE ASSEMBLY REMOVAL AND INSTALLATION

Номер: US20200368860A1
Принадлежит:

Dry tube tooling systems can manipulate dry tubes in reactors without removing all fuel next to the tubes, saving considerable outage time and allowing fresh detectors and instrumentation to be installed throughout fuel shuffling. Bodies of the tooling fits through a top guide and secure to the same without completely surrounding the dry tube or requiring all nearby fuel to be removed. The tooling includes a retainer that moves to secure to the dry tube and vertically and/or horizontally move the same. The retainer can release or install the dry tube in a fixed core location through such movement. Dry tubes can thus be installed and/or removed by operating the tooling from a bridge or crane above the reactor. The movement of the retainer can be achieved by power or signals from the operators to move and grasp the dry tube in a desired manner. 1. A method of manipulating a dry tube in a nuclear reactor , the method comprising:removing fuel assemblies directly adjacent to the dry tube such that at least one assembly remains directly adjacent to the dry tube;inserting a dry tube manipulation tool adjacent to the dry tube and opposite of the at least one remaining assembly;attaching a retainer of the tool to the dry tube; andremoving the tool and the attached dry tube from a position adjacent to the at least one remaining fuel assembly.2. The method of claim 1 , wherein the inserting includes lowering the tool from above the nuclear reactor such that the tool is completely submerged in coolant in the nuclear reactor.3. The method of claim 1 , wherein the removing includes vertically depressing a plunger on the dry tube to nondestructively disconnect the dry tube from a top guide in the nuclear reactor.4. The method of claim 3 , wherein the vertically depressing includes vertically moving the retainer downward with respect to a body of the tool.5. The method of claim 1 , wherein the tool includes a plurality of wings attached to a body of the tool and shaped to fit ...

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17-12-2020 дата публикации

METHOD OF CLEANING A THROAT SECTION OF A JET PUMP ASSEMBLY OF A NUCLEAR REACTOR

Номер: US20200391254A1
Принадлежит: GE-HITACHI NUCLEAR ENERGY AMERICAS LLC

A method of cleaning a jet pump assembly of a nuclear reactor may comprise inserting a cleaning tool into the jet pump assembly such that a front face of the cleaning tool is adjacent to an inner surface of the jet pump assembly and below a level of a first liquid in the jet pump assembly. The method may additionally comprise directing a plurality of front jets of a second liquid from a plurality of front orifices on the front face of the cleaning tool such that the plurality of front jets of the second liquid strikes the inner surface of the jet pump assembly. The method may further comprise maintaining a standoff distance between the front face of the cleaning tool and the inner surface of the jet pump assembly during the cleaning of the jet pump assembly. 1. A method of cleaning a jet pump assembly of a nuclear reactor , comprising:inserting a cleaning tool into the jet pump assembly such that a front face of the cleaning tool is adjacent to an inner surface of the jet pump assembly and below a level of a first liquid in the jet pump assembly;directing a plurality of front jets of a second liquid from a plurality of front orifices on the front face of the cleaning tool such that the plurality of front jets of the second liquid travel through the first liquid and strike the inner surface of the jet pump assembly; andmaintaining a standoff distance between the front face of the cleaning tool and the inner surface of the jet pump assembly during the cleaning of the jet pump assembly.2. The method of claim 1 , wherein the inserting includes connecting the cleaning tool to a bent wand and lowering the cleaning tool into a secondary inlet opening of the jet pump assembly via the bent wand.3. The method of claim 1 , wherein the inserting includes connecting the cleaning tool to a hose claim 1 , mounting a manipulation tool on a rim of an inlet mixer of the jet pump assembly claim 1 , and bending the hose and lowering the cleaning tool into a secondary inlet opening of ...

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26-12-2019 дата публикации

INSPECTION VEHICLE WITH MAINTENANCE TOOLS

Номер: US20190389548A1
Принадлежит:

An inspection vehicle operable for performing one or more maintenance and repair operations in a housing filled at least partially with a liquid medium is disclosed in the present application. The inspection vehicle includes a propulsion device operable in the liquid medium and includes at least one sensor operable for sensing and transmitting data associated therewith. A control system including an electronic controller is in electronic communication with the inspection vehicle to transmit and receive communication signals to/from the inspection vehicle. One or more maintenance tools operable with the inspection vehicle are configured to perform maintenance and/or repair operations within the liquid filled housing. 1. An inspection system comprising:an inspection vehicle having a propulsion device operable in an enclosed tank at least partially filled with a liquid medium;at least one sensor operable with the inspection vehicle;a control system including an electronic controller in electronic communication with the inspection vehicle; andone or more maintenance tools operable with the inspection vehicle.2. The inspection system of claim 1 , wherein the one or more maintenance tools includes at least one of a suction pump claim 1 , a grasping device claim 1 , a cutting device claim 1 , an impact device claim 1 , a magnet claim 1 , a welder and a rotary tool.3. The inspection system of claim 2 , wherein the suction pump is in fluid communication with an inlet port formed in a housing of the inspection vehicle.4. The inspection system of claim 1 , further comprising an outlet port formed in the housing of the inspection vehicle claim 1 , the outlet port in fluid communication with the inlet port.5. The inspection system of claim 4 , wherein the suction pump is operable for drawing in a quantity of the liquid with entrained solid particulate through the inlet port and for discharging the liquid and solid particulate through the outlet port.6. The inspection system of ...

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08-10-1993 дата публикации

Procédé et installation de contrôle non destructif d'une pièce utilisant un capteur à courants de foucault.

Номер: FR2689637A1
Принадлежит: AIRBUS GROUP SAS

Dans une installation de contrôle non destructif d'une pièce (10) telle qu'une pièce en matériau composite, on balaye la surface (12) de la pièce avec un capteur à courants de Foucault (10) dont on extrait des signaux de sortie représentant les parties réelle (Rc n ) et imaginaire (Xc n ) normalisées de l'impédance de mesure normalisée (Zc n ) de ce capteur. A partir de ces signaux de sortie, un ordinateur (30) calcule une première valeur (alpha) représentative de la distance (d) capteur-surface et indépendante de la conductivité (sigma) de la pièce, et une deuxième valeur (theta) représentative de la conductivité (sigma) et indépendante de la distance (d). A partir de paramètres obtenus lors d'une opération d'apprentissage préalable l'ordinateur (30) calcule ensuite la distance (d) et la variation relative (CF DESSIN DANS BOPI) de la conductivité de la pièce, par rapport a une zone de référence de celle-ci.

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24-11-2022 дата публикации

Containment apparatus monitoring system and method

Номер: US20220375637A1

Provided are containment apparatus monitoring system and method. The containment apparatus monitoring system includes at least one containment apparatus configured to contain nuclear material and generate containment information including integrity information and radiation information, a converter configured to collect the containment information from the containment apparatus, and a control server configured to analyze integrity of the nuclear material and a radiation state in the containment apparatus by using the containment information collected from the converter and monitor whether the containment apparatus is abnormal by using the analyzed result.

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09-07-2013 дата публикации

증기발생기 배관 파단 모의실험 방법 및 장치

Номер: KR20130077607A
Принадлежит: 두산중공업 주식회사

본 발명은 압력경계가 되는 증기발생기의 배관이 파단됨으로써 일어나는 현상을 모의 실험을 통해 확인할 수 있는 모의실험 방법 및 장치에 관한 것이다. 본 발명의 증기발생기 배관 파단 모의실험장치의 일 실시예는, 모의 증기발생기측에 연결되는 제1배관; 상기 제1배관에 연결되는 중간배관; 상기 중간배관에 연결되는 제2배관; 상기 제1배관과 중간배관 사이에 구비되어 차폐하는 제1럽쳐디스크; 상기 중간배관과 제2배관 사이에 구비되어 차폐하는 제2럽쳐디스크;를 포함한다.

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21-09-2021 дата публикации

一种核电厂蒸汽发生器的监测方法及系统

Номер: CN113418661A
Принадлежит: China Nuclear Power Engineering Co Ltd

本发明公开一种核电厂蒸汽发生器的监测方法,包括:建立蒸汽发生器模型,并在所述蒸汽发生器模型内模拟未发生泄漏时的蒸汽发生器内的放射性响应三维分布,以得到模拟的未发生泄漏时的放射性响应三维分布;在蒸汽发生器的内部或外部预设探测点,用于检测所述探测点的实际放射性强度值A i ;根据所述模拟的未发生泄漏时的放射性响应三维分布,确定所述探测点在未发生泄漏时的正常放射性强度值A i0 ;将实际放射性强度值A i 与正常放射性强度值A i0 进行比较,根据A i 与A i0 的比较结果判断蒸汽发生器内是否发生泄漏。本发明还公开一种核电厂蒸汽发生器的监测系统。本发明可对蒸汽发生器进行在线监测,能够快速判断蒸汽发生器的传热管是否发生放射性泄漏。

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07-06-2012 дата публикации

Apparatus and Method for detecting the wall thinning of pipeline using pulse magnetic field

Номер: KR101150486B1
Автор: 김흥회, 박덕근, 정용무

본 발명에 따른 펄스유도자속을 이용한 배관감육 탐상장치는, 펄스자기장을 발생시킴에 따라 배관에 유도되는 펄스유도자속을 자기센서로 측정하여, 상기 배관을 감싸는 절연재 외부에서 상기 배관의 감육 또는 두께변화 검사가 가능하며, 구체적으로, 피검체와 이격되어 비접촉하는 자화요크; 상기 자화요크에 권취되어, 상기 피검체에 펄스자기장을 형성시키는 코일부; 상기 코일부에 전기적으로 연계되어, 상기 코일부에 펄스전원을 공급하는 전원공급부; 상기 자화요크에 설치되며, 상기 펄스자기장에 의해 상기 피검체에 유도되는 펄스유도자속을 탐지하면서 상기 펄스유도자속의 변화를 검출하여 측정신호를 발생시키는 자기센서; 상기 자기센서에서 발생된 상기 측정신호를 수신하여 증폭 및 필터링하는 증폭회로; 및 상기 증폭회로에 의해 증폭 및 필터링된 측정신호를 수신 및 처리하여 상기 피검체의 감육 및 두께변화를 산출하는 신호처리부;를 포함한다. In the pipe thinning flaw detection apparatus using the pulse induction magnetic flux according to the present invention, the pulse induction magnetic flux induced in the pipe as the pulse magnetic field is generated by measuring with a magnetic sensor, the thickness or thickness change of the pipe outside the insulating material surrounding the pipe Inspection is possible, specifically, magnetized yoke that is spaced apart from the subject to contact; A coil unit wound around the magnetizing yoke to form a pulse magnetic field on the subject; A power supply unit electrically connected to the coil unit to supply pulse power to the coil unit; A magnetic sensor installed in the magnetizing yoke and detecting a change in the pulse induction flux while detecting a pulse induction flux induced in the subject by the pulse magnetic field to generate a measurement signal; An amplifier circuit for receiving, amplifying and filtering the measurement signal generated by the magnetic sensor; And a signal processor configured to receive and process a measurement signal amplified and filtered by the amplification circuit to calculate a thickness and a thickness change of the subject.

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26-05-2020 дата публикации

Inspection equipment for ct/lin gap measurement of pressurized heavy water reactor

Номер: KR102101495B1
Принадлежит: 한국수력원자력 주식회사

중수로 칼란드리아관과 액체물질 주입관의 간격측정을 위한 검사장비가 개시된다. 본 발명은 일정한 길이로 연장되어 칼란드리아 원자로 내부로 삽입되는 연결부와 상기 연결부의 일측에 구비되어 원자로 내부에 설치된 배관의 상태를 확인 가능하게 마련되는 육안검사부와 상기 연결부의 타측에 구비되어 상기 배관의 상태를 측정하기 위해 레이저 광원을 제공하는 레이저검사부; 및 상기 육안검사부의 하단에 일정한 각도 범위 내에서 회전가능하게 구비되는 반사거울을 포함하며, 본 발명에 의하면 실시간으로 칼란드리아관 내부의 영상 관측, 저장 및 평가가 가능하고, 레이저를 통해 관측값을 보정하거나 보다 정확한 측정이 가능할 것이다. Disclosed is an inspection device for measuring the gap between a Kalandria tube and a liquid material injection tube. The present invention is provided on one side of the connecting portion extending into a constant length and inserted into the Kalandria reactor and the connecting portion is provided on the other side to check the state of the pipe installed inside the reactor and the other side of the connecting portion provided on the other side of the pipe A laser inspection unit providing a laser light source to measure a state; And a reflective mirror rotatably provided within a certain angular range at the bottom of the visual inspection unit, According to the present invention, image observation, storage, and evaluation inside the Kalandria tube can be performed in real time, and observation values can be corrected or more accurately measured through a laser.

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23-03-1992 дата публикации

Device for eddy-current inspection of heat-exchanger with u- shaped tubes

Номер: SU1722252A3
Принадлежит: Сименс Аг (Фирма)

The leading tip of an eddy current testing probe (1) is connected to a feed tube (6) via elastic tube sections (3a - 3m) with a plurality of coils (4a - 4h) inserted in between. Said feed tube (6) can be pushed into a tube in the bundle to be tested by means of a feed device. The pressure-contact surfaces (9) of the coils (4a - 4h) each extend over only a section of the internal circumference of the tube and the coils (4a - 4h) are offset with respect to one another at the circumference of the testing probe (1) and in the longitudinal axis of the probe. A position-detection unit (25) is fitted in the testing probe (1). The apparatus according to the invention can be used to test even those tubes which have a narrow radius of curvature, flaws being located by a length and angle indication. …<IMAGE>…

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30-11-2001 дата публикации

Stress Corrosion Monitoring System of Vessel Penetrating Members and Degradation Evaluation Method of Penetrating Members

Номер: KR100306332B1

응력-부식 손상은 전해액(50)을 수용하는 용기의 벽(40)을 가로지르는 관통구조물(32)내에서 추적된다. 이러한 용기는 냉각제를 수용하는 원자로 압력용기와 같은 것을 말한다. 상기 용기의 벽(40)은 압력차단벽을 유지하면서 용기의 내부 구조물에 외부장치를 결합하기 위하여 제어봉 안내장치 및 센서 신호와 케이블과 같은 관통 튜브(32)를 갖는다. 상기 관통구조물(32)은 응력-부식 손상되며 특히 상기 관통구조물을 상기 용기헤드에 부착한 용접부 근처에서 그러하다. 1개 또는 그 이상의 관통구조물(32)은 상기 관통구조물과 함께 전기화학적 센서 셀을 형성하는 센서 탐침으로 구성되는데, 상기 관통구조물(32) 벽(82)의 표면과 함께 전해액(50)에 노출된 전극(74)을 구비한다. 상기 전극(74) 및 상기 표면은 달리 절연되며, 다수의 전극(64)은 별개의 국소 영역을 추적하기 위하여 배열될 수 있다. 상기 전극(72, 74)은 응력 및 부식으로 인한 전기화학적 활성의 작용으로서의 신호를 생성하는 검출회로에 결선되며, 모든 관통구조물의 부식을 나타낸다. 전기화학적 전위, 임피던스, 전류 및 이러한 신호의 특정 노이즈 수준은 전기화학적 활성의 작용으로서의 관통구조물 벽의 노후화를 평가하기 위하여 검출되고 판독된다. Stress-corrosion damage is tracked in the through structure 32 across the wall 40 of the vessel containing the electrolyte 50. Such a container refers to something like a reactor pressure vessel containing a coolant. The wall 40 of the vessel has control rod guides and through tubes 32 such as cables and sensor signals for coupling the external devices to the vessel's internal structure while maintaining the pressure barrier wall. The through structure 32 is stress-corrosion damaged, especially near the weld that attaches the through structure to the vessel head. One or more of the through structures 32 consists of a sensor probe that forms an electrochemical sensor cell with the through structures, which are exposed to the electrolyte 50 together with the surface of the walls 82 of the through structures 32. An electrode 74 is provided. The electrode 74 and the surface are otherwise insulated, and a plurality of electrodes 64 can be arranged to track separate local areas. The electrodes 72, 74 are connected to a detection circuit that generates a signal as a function of electrochemical activity due to stress and corrosion, indicating corrosion of all through structures. Electrochemical potentials, impedances, currents and specific noise levels of these signals are detected and read out to assess aging of the through-structure wall as a ...

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27-11-2012 дата публикации

Method of measuring pressure and/or molar mass of gas inside enclosure and measuring device

Номер: RU2468362C2

FIELD: physics. SUBSTANCE: measurements are taken using an acoustic sensor having at least one transducer (5), an electrical system (8) connected to the transducer (5), and a connecting layer (6) for connecting the transducer (5) to an enclosure (1), and the method involves the transducer (5) generating an exciting acoustic signal which causes vibration of the enclosure (1) and the gas (2) in a wide frequency range; detecting, by the transducer (5), a response acoustic signal characterising vibrations of the enclosure and the gas; analysing response electrical signals coming from the transducer (5) using the system (8) and determining, in particular, using resonance frequencies of the gas (2), the speed of propagation of acoustic waves in the gas, the molar mass of the gas and its pressure. EFFECT: possibility of obtaining pressure values in a cylindrical enclosure filled with a gaseous mixture with high measurement accuracy, possibility of determining molar mass of said gaseous mixture with high measurement accuracy. 12 cl, 7 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) 2 468 362 (13) C2 (51) МПК G01N 29/00 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (21)(22) Заявка: 2009131682/28, 25.01.2008 (24) Дата начала отсчета срока действия патента: 25.01.2008 (43) Дата публикации заявки: 10.03.2011 Бюл. № 7 (56) Список документов, цитированных в отчете о поиске: FR 2739925 A1, 18.04.1997. WO 0073781 A1, 07.12.2000. GB 1483321 A, 17.08.1977. SU 1758457 A1, 30.08.1992. SU 1064171 A1, 30.12.1983. RU 30980 U1, 10.07.2003. 2 4 6 8 3 6 2 R U (86) Заявка PCT: EP 2008/050864 (25.01.2008) C 2 C 2 (85) Дата начала рассмотрения заявки PCT на национальной фазе: 26.08.2009 (87) Публикация заявки РСТ: WO 2008/095793 (14.08.2008) Адрес для переписки: 191186, Санкт-Петербург, а/я 230, "АРСПАТЕНТ", пат.пов. М.В.Хмаре, рег. № 771 (54) СПОСОБ ИЗМЕРЕНИЯ ДАВЛЕНИЯ И/ИЛИ МОЛЯРНОЙ МАССЫ ГАЗА ВНУТРИ ОБОЛОЧКИ И ИЗМЕРИТЕЛЬНОЕ УСТРОЙСТВО (57) Реферат: ...

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28-06-2012 дата публикации

Loading apparatus of steam generation inspection robot

Номер: KR101160660B1

본 발명은 상단에 원자력 발전용 증기 발생기의 전열관에 삽입되는 삽입핀이 설치되며, 상기 증기 발생기의 일측에 형성된 개구로 삽입된 가이드 레일과, 상기 가이드 레일을 상기 증기 발생기의 개구 일측에 고정시키는 가이드 고정유닛 및 상기 가이드 레일을 따라 이동하면서 상기 전열관을 검사하는 검사로봇이 장착되는 이송유닛을 포함하는 것을 특징으로 하는 전열관 검사로봇의 입퇴실장치에 관한 것이다. 이에, 본 발명은 핵분열에서 발생하는 에너지를 이용하여 증기를 발생시키는 전열관을 검사하는 검사로봇을 증기발생기의 내부로 인입시키고, 인출시키도록 하되, 정교하게 그 위치를 조절할 수 있도록 하여 검사로봇이 정확하게 전열관을 검사할 수 있도록 증기 발생기의 개구에 가이드 레일을 고정시켜 가이드 레일을 따라 검사로봇을 증기발생기의 내부로 이송시키도록 이루어짐에 따라 검사로봇을 증기 발생기의 내부로 이송시키기 용이하고, 정확한 위치로 이송시킬 수 있는 효과가 있다. The present invention has an insertion pin is inserted into the heat transfer tube of the steam generator for nuclear power generation at the top, a guide rail inserted into the opening formed on one side of the steam generator, and a guide for fixing the guide rail to the opening side of the steam generator It relates to the entrance and exit device of the heat transfer tube inspection robot, characterized in that it comprises a transfer unit is mounted to the inspection robot for inspecting the heat transfer pipe while moving along the fixed unit and the guide rail. Therefore, the present invention is to introduce the inspection robot for inspecting the heat transfer tube that generates steam by using the energy generated from the nuclear fission into the steam generator, and to draw out, but to precisely control the position so that the inspection robot accurately The guide rail is fixed to the opening of the steam generator so that the heat pipe can be inspected, and the inspection robot is moved along the guide rail to the inside of the steam generator. There is an effect that can be transferred.

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07-06-2022 дата публикации

On-line system for providing method for verifying quality of air operating valve using in nuclear power plant

Номер: KR102404852B1
Автор: 김한수, 윤현석, 허남용
Принадлежит: 한국수력원자력 주식회사

본 발명은 원자력 발전소에 사용되는 공기 구동 밸브의 품질 검증방법에 대한 온라인 시스템에 관한 것으로, 검증방법에 대한 정보가 포함되어 있는 데이터 베이스; 상기 데이터 베이스와 연결되어 있는 웹서버; 상기 웹서버에 온라인으로 연결되어 있는 사용자 단말기를 포함하며, 상기 웹서버는 상기 사용자 단말기에 공기 구동 밸브의 품질 검증방법에 대한 정보를 제공한다.

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23-03-2022 дата публикации

Method for measuring the deflection of the technological channel of a nuclear reactor

Номер: RU2768260C1

FIELD: measuring technologies. SUBSTANCE: present invention relates to a method for measuring the deflection of a technological channel of a nuclear reactor. The method includes placing at least one fiber optic sensor fixed at the end of a flexible hollow carrier rod inside the central tube of a fuel assembly, supplying a light signal via fiber optic lines connected to the sensor, recording reflected light signals using a fiber optic sensor connected to the fiber optic lines of photodetector. The determination of the deflection of the technological channel of a nuclear reactor is carried out on the basis of an analysis of the parameters of the light signal. Wherein a fiber-optic sensor is used, equipped with a gravitational pendulum suspended with the possibility of deflection at the lower end of the fiber-optic sensor, a flexible hollow bearing rod is moved with a fiber-optic sensor along the central heat-generating tube, a shift of the interference pattern of the reflected light signal in the gas gap between the upper end is fixed. the surface of the gravitational pendulum and the lower end surface of fiber-optic lines connected to the photodetector and fixed on the sensor. Further, based on the profilograms of the gas gap, the magnitude and direction of the deflection of the central tube of the fuel assembly from the vertical axis are calculated, which are used to judge the presence and magnitude of the deflection of the technological channel of the nuclear reactor. EFFECT: simplification of measurements of the deflection of the technological channel of a nuclear reactor while maintaining the measurement accuracy. 1 cl, 4 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 768 260 C1 (51) МПК G21C 17/017 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 17/017 (2022.02) (21)(22) Заявка: 2021128446, 29.09.2021 (24) Дата начала отсчета срока действия патента: Дата регистрации: 23.03.2022 (45) Опубликовано: 23. ...

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07-04-2017 дата публикации

Device for detecting and removing of foreign objects in steam generator

Номер: KR101724987B1
Принадлежит: 한전케이피에스 주식회사

The present invention relates to a residue inspection and removal device for a steam generator comprising: a main body provided to be movable by a driving unit; a flexible guide made of bendable material having force of restitution and having a first monitoring unit installed on an end portion; and a feeding unit installed on an upper portion of the main body, having an insertion hole into which the flexible guide is inserted, and moving the flexible guide inserted into the insertion hole toward or away from the main body. According to an embodiment of the present invention, a flexible guide is inserted into a heat transfer pipe of a steam generator to monitor whether foreign substances exist in a gap between the heat transfer pipes and to remove the foreign substances.

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20-11-2013 дата публикации

Method for making test specimen and test equipment to evaluate the safety of piping

Номер: KR20130126014A
Автор: 석창성
Принадлежит: 성균관대학교산학협력단

본 발명은 배관의 안정성 평가용 시험장치에 관한 것이며, 본 발명의 배관의 안정성 평가용 시험장치는 원자력 발전소에 사용되는 배관의 안정성 평가용 시험장치에 있어서, 상기 배관과 동일한 소재로 형성되며, 단부인 제1면으로부터부터 절개되어 노치부가 형성되고, 상기 노치부의 단부에는 균열부가 형성되는 시편; 상기 시편과 연결되어, 상기 노치부가 절개된 방향에 수직한 방향으로 하중을 인가하는 하중인가부;를 포함하며, 상기 하중인가부와 연결되는 한 쌍의 핀홀이 상기 시편 상에 인가되는 하중 방향을 따라 상호 이격되게 형성되되, 상기 제1면에 대향하는 제2면과 상기 균열부의 단부 사이의 공간에 중심점이 마련되는 것을 특징으로 한다. 따라서, 본 발명에 의하면, 하중 인가시에 실제 시공되는 배관과 동일한 응력구배를 갖는 시편을 이용하여 높은 신뢰성의 안정성 평가를 실시할 수 있는 배관의 안정성 평가용 시험장치이 제공된다.

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27-08-2021 дата публикации

Testing device and method for function verification of secondary loop water supply system of nuclear power station

Номер: CN113314242A

一种用于核电站二回路给水系统功能验证的测试装置及方法,包括除氧器、给水前置泵入口隔离阀、给水前置泵、主给水泵、备用给水泵、最小流量再循环阀、主给水隔离阀、主给水调节阀、蒸汽发生器、除氧器液位监测装置和给水流量监测装置。核电站二回路给水系统各测试信号分别通过核电站二回路给水系统DCS机柜经PXI数据采集机柜与仿真建模服务器相连。本发明能够实现对核电站二回路给水系统实际功能的提前验证,并提高测试效率。

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20-06-2012 дата публикации

Method and apparatus for an expanding split bushing pipe plug assembly

Номер: EP2466184A1
Принадлежит: GE HITACHI NUCLEAR ENERGY AMERICAS LLC

A method and apparatus for securely fastening a pipe collar or a bracket to a riser pipe (51) of a boiling water reactor (BWR) jet pump assembly (50). A pipe plug assembly (1) includes an angled pipe plug (14) that acts as a wedge to expand a bushing assembly (16) as the pipe plug (14) is drawn into the overall pipe plug assembly (1). Expansion of the bushing assembly (16) allows a tight tolerance to exist between an outer diameter of the pipe plug (14) and an inner diameter of the collar / bracket and riser pipe (51). Expansion of the bushing assembly (16) allows a straight hole to be match drilled into the collar / bracket and riser pipe (51), thereby avoiding a more complicated tapered hole to be drilled into the collar / bracket and riser pipe (51). An ensuing tight fit between the pipe plug assembly (1), the collar / bracket and the riser pipe (51) mitigates vibration of components and minimizes leakage to acceptable levels for use in the flooded environment of the annulus region where the jet pump assembly (50) exists in the BWR.

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01-06-2010 дата публикации

Device for monitoring leakage of steam generator for atomic power plant and method thereof

Номер: KR100960787B1
Автор: 강덕원, 손욱
Принадлежит: 한국전력공사

이 발명은, 핵종 분석이 불가능한 총베타 방사선 감시기를 사용하는 것이 아니라, 특정 핵종인 Ar-41만을 감지해낼 수 있는 감마선 방사선 측정기를 사용함으로써 핵분열성 생성물에 의한 영향이 없이 누설을 감지할 수 있도록 하여 누설 감시에 대한 감도를 높일 수 있으며, 소규모 누설감지에도 적용할 수가 있는 원자력 발전소의 증기발생기의 누설 감지장치 및 방법에 관한 것으로서, Instead of using a total beta radiation monitor that does not allow for nuclide analysis, the invention uses a gamma-ray radiometer that can detect only a specific nuclide, Ar-41, so that leakage can be detected without the impact of fissile products. The present invention relates to a leak detection device and method for a steam generator of a nuclear power plant that can increase sensitivity to leak monitoring and can be applied to small leak detection. 배기개스 계통 배관에 설치되어 있으며 Ar-41의 방출 감마선 에너지만을 측정하도록 설치되어 있는 감마 방사선 측정기와, 상기한 감마 방사선 측정기에 의해 측정된 Ar-41의 감마선 신호를 증폭하기 위한 프리앰플리파이어와, 상기한 프리앰플리파이어에 의해 증폭된 Ar-41의 감마선 신호를 방사능 수치로 변환하기 위한 레이트미터와, 상기한 레이트미터로부터 입력되는 방사능 신호를 이용하여 방사능의 누설율을 산출하여 표시하기 위한 컴퓨터와, 배기개스 계통 배관에 설치되어 배기개스 계통 배관내의 유체의 양을 측정하기 위한 유량계를 포함하여 이루어진다. A gamma radiation meter installed in the exhaust gas system pipe and installed to measure only the emission gamma ray energy of Ar-41, a preamplifier for amplifying the gamma ray signal of Ar-41 measured by the above-mentioned gamma radiation meter, and A rate meter for converting the gamma-ray signal of the Ar-41 amplified by a preamplifier into a radiation value, a computer for calculating and displaying the leakage rate of radiation using the radiation signal inputted from the rate meter, and an exhaust gas. It is installed in the gas system piping and includes a flow meter for measuring the amount of fluid in the exhaust gas system piping. 감마선, 방사선, 플리앰플리파이어, 레이트미터, 컴퓨터, 유량계 Gamma Rays, Radiation

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30-03-2016 дата публикации

System and method for monitoring fatigue of nuclear power plant

Номер: CN105448359A

本发明公开了一种核电厂疲劳监测系统及方法,属于核电技术领域。所述系统包括:温度数据获取子系统,用于测量疲劳敏感区域的管道或设备的外壁面温度,以获取外壁面温度参数;核电厂数字化仪控子系统,用于获取所述管道或设备中流体温度参数和流体压力参数;疲劳监测服务器,用于接收温度数据获取子系统传送的外壁面温度参数及核电厂数字化仪控子系统传送的流体温度参数和流体压力参数,并基于所述外壁面温度参数、所述流体温度参数和所述流体压力参数计算获得所述管道或设备的真实疲劳状态。本发明通过对核电厂典型疲劳敏感区域的金属管道或设备进行实时监测,以获得管道或设备的真实疲劳状态,用以对可能存在疲劳损坏的管道或设备进行预警。

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17-05-2017 дата публикации

Pipe inspecting apparatus and pipe inspecting method

Номер: KR101737216B1
Принадлежит: 가부시끼가이샤 도시바

일실시형태에 의하면, 배관 검사 장치는, 배관에 장착된 복수의 초음파 광프로브 중에서 제1 및 제2의 초음파 광프로브를 선택하는 선택부를 구비한다. 또한, 상기 장치는, 상기 제1의 초음파 광프로브의 초음파 발진자에 전력을 공급하여, 상기 초음파 발진자로부터 상기 배관에 초음파를 입력하고, 상기 초음파를 상기 배관을 개재하여 상기 제2의 초음파 광프로브의 광섬유 센서에 공급하는 전력 공급부를 구비한다. 또한, 상기 장치는, 상기 제2의 초음파 광프로브의 상기 광섬유 센서 중을 투과한 레이저광을 검출하는 광검출부를 구비한다. According to one embodiment, the piping inspection apparatus includes a selection unit that selects the first and second ultrasonic optical probes from a plurality of ultrasonic optical probes mounted on the piping. In addition, the apparatus may further include a controller for supplying power to the ultrasonic oscillator of the first ultrasonic optical probe, inputting ultrasonic waves from the ultrasonic oscillator to the pipe, and transmitting the ultrasonic wave to the second ultrasonic optical probe And a power supply unit for supplying the optical fiber sensor. The apparatus further includes a photodetector for detecting the laser beam transmitted through the optical fiber sensor of the second ultrasonic optical probe.

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05-12-2016 дата публикации

Water jet peening device and method for executing water jet peening

Номер: KR101682846B1

워터젯 피닝 장치 및 워터젯 피닝 시공 방법에 있어서, 계장 관대(83)의 외주부측에 소정 간극을 두고 배치 가능한 클램프통(201)과, 클램프통(201)을 계장 관대(83)에 고정 가능한 클램프편(210)과, 원통 형상을 이루어 클램프통(201) 내에 설치되어서 계장 관대(83)의 상단부에 근접한 위치에 위치 결정되는 노즐 가이드(221)와, 노즐 가이드(221)의 내부를 승강 가능한 내면 WJP 노즐(105)과, 노즐 가이드(221)를 방사 형상으로 관통하는 배수 구멍(224)을 마련함으로써, 워터젯 피닝에 의한 심블 튜브의 튀어나옴을 방지해서 작업의 안전성 향상을 가능하게 한다. A clamping device for a water jet pinning apparatus and a water jet peening method, comprising: a clamp tube (201) that can be disposed with a predetermined gap therebetween on an outer peripheral side of a instrument chain bar (83) A nozzle guide 221 provided in the clamping cylinder 201 in a cylindrical shape and positioned at a position close to the upper end of the instrument bench 83, and an inner WJP nozzle And a drain hole 224 penetrating radially through the nozzle guide 221 are provided so as to prevent the thimbles from protruding due to water jet pinning, thereby making it possible to improve work safety.

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04-02-2015 дата публикации

Radioactive nuclide gamma activity online measuring system

Номер: CN104332198A
Принадлежит: China Institute of Atomic of Energy

本发明提供了一种放射性核素γ活度在线测量系统,该系统包括:γ射线探测器、γ谱仪和计算机,所述γ射线探测器用于获取与核电厂一回路系统相连的辅助系统管道中各种放射性核素γ活度数据,所述γ谱仪用于从所述γ射线探测器获取所述各种放射性核素γ活度数据后进行核素的全能谱分析,所述计算机用于获取所述γ谱仪的分析结果并对该分析结果进行处理。该系统可布置在核电厂辅助厂房,通过γ射线探测器中的高纯锗γ探头对准与核电厂一回路系统相连的辅助系统管道,可在不接触、不破坏回路系统压力边界的情况下进行测量,不影响反应堆本身安全。

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22-06-2018 дата публикации

Noncontact Vibration Monitoring System for Small Diameter Plumbing Pipes for nuclear power plants of capable of Self-Vibration Correction

Номер: KR101870381B1
Принадлежит: 케이.엘.이.에스 주식회사

The present invention relates to a non-contact vibration monitoring system for a small diameter pipe of a nuclear power plant capable of realizing self-vibration calibration and, more specifically, to a non-contact vibration monitoring system for a small diameter pipe of a nuclear power plant capable of realizing self-vibration calibration, measuring vibration of a structure or pipe difficult for a worker to access due to radiation exposure in the nuclear power plant, so as to predict and prevent breakage of the structure of the pipe, and quickly cope with a breakage accident when the breakage accident occurs. To this end, the system comprises: a sensor support; a sensor fixing jig installed on an upper part of the sensor support; a non-contact vibration sensor installed on the upper part of the sensor fixing jig; a contact vibration sensor installed in the sensor fixing jig to measure self-vibration of the sensor fixing jig; and a calibration calculation unit calibrating the self-vibration measured in the contact vibration sensor from a vibration value measured in the non-contact vibration sensor.

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09-12-2019 дата публикации

Improved ultrasound inspection

Номер: KR102053800B1

실질적으로 원통 형상 물체를 초음파 스캔하는 장치 및 방법에서, 상기 장치는, 물체의 둘레 주위에 체결되도록 된 커프, 상기 커프의 내측 둘레에 대하여 장착되며 물체의 둘레를 스캔하도록 배치된 초음파 탐침, 상기 초음파 탐침에 대한 제어 정보를 제공하며 상기 초음파 탐침으로부터 스캔 데이터를 수신하는 하나 이상의 데이터 연결부를 포함한다. 상기 탐침은 방향이나 위치를 결정하는 하나 이상의 센서를 포함하며, 이러한 데이터는 상기 배열로부터 데이터를 처리하고 상기 장치의 작동을 제어하는데 사용된다. In an apparatus and method for ultrasonically scanning a substantially cylindrical object, the apparatus includes a cuff adapted to be fastened around a perimeter of the object, an ultrasonic probe mounted about the inner perimeter of the cuff and arranged to scan the perimeter of the object, the ultrasonic wave One or more data connections providing control information about the probe and receiving scan data from the ultrasonic probe. The probe includes one or more sensors that determine the direction or position, and this data is used to process data from the array and to control the operation of the device.

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06-08-2019 дата публикации

System for responding to loss of coolant accident

Номер: KR102007252B1
Автор: 수하이브, 허재석
Принадлежит: 한국원자력연구원

본 발명은 냉각재 상실 사고 대응 시스템에 관한 것으로, 핫레그메인파이프, 인터미디어트메인파이프, 콜드레그메인파이프, 핫레그스패어파이프, 인터미디어트스패어파이프, 콜드레그스패어파이프, 및 메인파이프 중 적어도 어느 하나가 파단되어 냉각재 상실 사고가 발생하면 파단된 메인파이프의 유로를 폐쇄하고 매칭되는 스패어파이프의 유로를 개방시키는 제어부를 포함하여 구성되어, 냉각재 상실 사고 시 냉각재의 상실을 즉각적으로 차단할 수 있게 한다. The present invention relates to a system for responding to a loss of coolant, and includes a hot leg main pipe, an intermediate main pipe, a cold leg main pipe, a hot leg spare pipe, an intermediate spare pipe, a cold leg spare pipe, and a main pipe. If the at least one of the breaks occurs, the coolant loss accident occurs, including a control unit for closing the flow path of the broken main pipe and opening the flow path of the matched spare pipe, to prevent the loss of coolant immediately in the case of coolant loss accident To be able.

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17-03-2014 дата публикации

Method for measuring the pressure and/or molar mass of a gas in a housing, and corresponding measurement assembly

Номер: KR101374679B1

본 발명은 하우징에서 가스의 압력 및/또는 몰 질량을 측정하기 위한 방법에 관한 것으로, 상기 방법은 음향 센서를 통해 실행되고, 상기 음향 센서는 적어도 하나의 변환기(5), 상기 변환기(5)에 연결되는 전기 시스템(8), 및 하우징(1)에 상기 변환기(5)를 결합하는 결합층(6)을 포함하고, 상기 방법은 상기 변환기(5)를 이용하여 넓은 주파수 대역에서 상기 하우징(1)과 가스(2)를 진동시키는 여기 음향 신호를 발생시키는 단계; 상기 변환기(5)로 하우징과 가스 진동의 반응 음향 신호 특성을 검출하는 단계; 상기 시스템(8)을 이용하여 상기 변환기(5)로부터 반응 전기 신호를 분석하는 단계; 및 본질적으로 상기 가스(2) 공진 주파수에 기초하여 가스에서 음파의 속도, 가스의 몰 질량, 및 가스의 압력을 얻는 단계를 포함한다. 또한, 본 발명은 상기 방법을 구현하기 위한 어셈블리에 관한 것이다. The present invention relates to a method for measuring the pressure and / or molar mass of a gas in a housing, the method being carried out via an acoustic sensor, said acoustic sensor being connected to at least one transducer (5), said transducer (5). An electrical system 8 to be connected, and a coupling layer 6 coupling the transducer 5 to the housing 1, wherein the method uses the transducer 5 in a wide frequency band. Generating an excitation acoustic signal that vibrates the gas 2; Detecting reactive acoustic signal characteristics of the housing and gas vibrations with the transducer (5); Analyzing the reactive electrical signal from the transducer (5) using the system (8); And essentially obtaining the velocity of sound waves in the gas, the molar mass of the gas, and the pressure of the gas based on the gas 2 resonant frequency. The invention also relates to an assembly for implementing the method. 어셈블리, 변화기, 질량, 공진 주파수, 하우징 Assembly, Transducer, Mass, Resonance Frequency, Housing

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28-02-2017 дата публикации

Circumferential sampling tool

Номер: KR101711170B1

관의 내벽으로부터 샘플을 얻기 위한 본 발명의 원주방향 샘플링 도구는 그 안에 개구를 갖는 원통형 몸체를 갖는다. 제 1 및 제 2 커터들은 그와 함께 회전하기 위해 샤프트(shaft)에 작동가능하게 연결되어 있다. 제 1 및 제 2 커터는 퇴축된 위치와 연장된 위치 사이에서 방사방향에서 각각 이동될 수 있다. 제 1 및 제 2 액츄에이터(actuator)들은 샤프트가 회전할 때 그 각각의 퇴축 및 연장 위치들 사이에서 제 1 및 제 2 커터들을 이동시키기 위해 제 1 및 제 2 커터들 각각에 작동가능하게 연결되어 있다. 샤프트를 회전시키면 제 1 커터가 연장 위치로 이동하게 하여 내벽의 일부분을 자른 다음에 제 2 커터가 연장 위치로 이동하게 하여 내벽의 부분을 잘라 드러난 관의 위치로부터 내벽으로부터 샘플을 절단하게 한다. The circumferential sampling tool of the present invention for obtaining a sample from the inner wall of a tube has a cylindrical body with an opening therein. The first and second cutters are operatively connected to a shaft for rotation therewith. The first and second cutters may be respectively moved in the radial direction between the retracted position and the extended position. The first and second actuators are operatively connected to each of the first and second cutters to move the first and second cutters between their respective retracted and extended positions as the shaft rotates . Rotating the shaft causes the first cutter to move to the extended position, cutting a portion of the inner wall, and then causing the second cutter to move to the extended position to cut the sample from the inner wall from the position of the tube cut out of the inner wall.

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18-02-2010 дата публикации

Inspecting Scanner Using Ultrasonic Wave

Номер: KR100943219B1
Принадлежит: (주)카이텍

검사시간을 단축시키고, 공간의 제약을 받지 않으면서 안정되게 검사를 수행할 수 있는 초음파 검사용 스캐너가 개시된다. 본 발명에 따른 초음파 검사용 스캐너는 배관 형태의 피검사체 외측에 제공되며, 상기 피검사체의 초음파 검사를 수행하는 초음파 센서가 구비된 본체, 상기 본체 상에 회전 가능하게 결합되어, 상기 피검사체의 외면을 따라 구름운동을 하는 복수 개의 이동바퀴 및 상기 복수 개의 이동바퀴 중 적어도 어느 하나를 구동시키는 구동유닛을 포함하여 구성된다. 따라서, 본 발명에 의하면 초음파 검사를 위해 별도의 구조물을 설치하지 않기 때문에 검사시간을 대폭적으로 단축시킬 수 있고, 주변공간이 협소한 곳에서도 사용이 가능하며 구조적으로 안정된 형태로 초음파 검사를 수행할 수 있다. 초음파, 피검사체, 바퀴, 곡률

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26-09-2014 дата публикации

Nondestructive Testing Apparatus and Method for Penetration Nozzle of Control Rod Drive Mechanism of Reactor Vessel Head

Номер: KR101444078B1
Автор: 이정률, 정효미, 최윤실
Принадлежит: 전북대학교산학협력단

원자로 상부헤드 제어봉 구동장치 비파괴 검사장치 및 방법이 제공된다. 본 발명의 실시예에 따른 비파괴 검사장치는, 레이저를 원자로 상부헤드와 제어봉 구동장치 관통관 사이의 용접부 및 제어봉 구동장치 관통관 내부로 스캐닝 조사하여 생성되는 초음파를 감지하고, 감지된 초음파를 영상화하되, 특정 영역의 다수 지점에 레이저가 스캐닝 조사되는 동안 초음파를 감지하는 초음파 센서의 위치는 변화가 없고 초음파전파영상화에 기반을 둔 손상가시화를 실시한다. 이에 의해, 검사시간이 현저히 감소하여 점검 시간 단축으로 이어져 직접적 경제적 효과로 나타난다. An apparatus and method for non-destructive inspection of a reactor head control rod drive apparatus are provided. The nondestructive inspection apparatus according to the embodiment of the present invention detects ultrasonic waves generated by scanning a laser to a welding portion between a reactor upper head and a control rod driving device pipe, and a control rod driving device pipe, and images the sensed ultrasonic waves , There is no change in the position of the ultrasonic sensor for detecting the ultrasonic waves while the laser is scanned at a plurality of points in the specific region, and the damage visualization based on the ultrasonic wave imaging is performed. As a result, the inspection time is significantly reduced, leading to a shortening of inspection time, resulting in a direct economic effect.

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24-01-2017 дата публикации

Prove Device Having Guiding Member for Extension Plate

Номер: KR101699357B1
Автор: 장종석, 조정
Принадлежит: 조정

According to the present invention, a probe device including a steel plate guiding member includes a feeding unit which is electrically connected to a probe head including an imaging module and allows a steel plate, extended in a lengthwise direction, to be wound therearound to be inserted and extracted. The feeding unit comprises: a bobbin which allows the steel plate to be wound therearound; a feeding frame which accommodates the bobbin and includes an accommodation space having an opening, formed on one side thereof, for discharging the steel plate to the outside; a first guiding member which is arranged in the opening, is arranged between a winding area and an extraction area of the steel plate, is joined to the feeding frame, and has a first facing surface formed in the direction of the steel plate; and a second guiding member which is separated from the first guiding unit, is arranged on the opening, forms a guide path, formed between the first guiding member and the same, for allowing the steel plate to be inserted and extracted, and has a second facing surface facing the first facing surface.

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10-01-2019 дата публикации

Method for repairing nozzle of RCS pipe in reactor

Номер: KR101937610B1
Автор: 김영주
Принадлежит: 한전케이피에스 주식회사

The present invention relates to a method for repairing a nozzle of a pipe in a nuclear reactor, and more specifically, to a method of repairing a nozzle which is welded to and installed on a pipe in a nuclear reactor, a welding base metal, and includes an upper nozzle portion with a first through hole, an orifice portion with a second through hole communicated with the first through hole, and a lower nozzle portion with a third through hole communicated with the second through hole. The method comprises: a step (a) of inserting a first plug into a lower end of the first through hole and removing a part of an upper nozzle portion on an upper side of the first plug; a step (b) of inserting a second plug into the second through hole and removing a residual upper nozzle portion and the orifice portion; a step (c) of inserting the third plug into the third through hole and welding a pad to a surface of the welding base metal; a step (d) of forming a j groove in an upper portion of the pad; a step (e) of removing the third plug inserted into the third through hole; a step (f) of installing a new nozzle on an upper side of a residual nozzle; and a nozzle welding step (g) of welding a space between the groove and an outer peripheral surface of the new nozzle. According to the present invention, the method is effective in preventing damages to the pipe, the welding base metal, in a nuclear reactor and removing a defective portion on a welded portion of the nozzle.

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26-10-2016 дата публикации

Reduce the internal mechanical stresses improved method of pipeline welding regional stress corrosion cracking

Номер: CN104854390B

用于在核能装置管道的内部(润湿侧)焊接区域缓解应力腐蚀开裂的方法,包括驱动径向可动工具以对焊接区域处或其附近的内部(即通常是湿的)表面上产生径向负载以形成残余应力状态。所述方法通过表面弯曲度的物理测量能够后流程验证。

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19-10-1982 дата публикации

Self-travelling manipulater used inside pipe

Номер: JPS57169674A
Принадлежит: Kraftwerk Union AG

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01-07-2021 дата публикации

Inspection apparatus for heat transfer pipe

Номер: KR102271732B1
Принадлежит: 두산중공업 주식회사

본 발명은 카메라를 갖는 검사 헤드를 원하는 방향으로 용이하게 이동시킬 수 있는 증기발생기 검사 장치를 제공한다. 본 발명의 일 측면에 따른 전열관 검사 장치는 상기 증기발생기의 내부에 삽입 배치되는 레일부, 카메라와 발광소자를 포함하는 검사 헤드, 상기 레일부를 따라 이동 가능하게 설치되며 상기 검사 헤드를 이동시키는 대차, 및 상기 검사 헤드와 전기적으로 연결되며 가요성을 갖는 복수의 보호관을 포함하는 관 결합체를 포함하고, 상기 보호관들은 복수의 접합부에 의하여 이웃하는 보호관에 고정되되 상기 접합부는 상기 관 결합체의 길이방향으로 이격 형성된다. The present invention provides a steam generator inspection apparatus capable of easily moving an inspection head having a camera in a desired direction. A heat transfer tube inspection apparatus according to an aspect of the present invention includes a rail part inserted and disposed inside the steam generator, an inspection head including a camera and a light emitting element, a bogie installed movably along the rail part and moving the inspection head; and a tube assembly electrically connected to the inspection head and including a plurality of flexible protective tubes, wherein the protective tubes are fixed to neighboring protective tubes by a plurality of joint portions, wherein the joint portions are spaced apart in the longitudinal direction of the tube assembly. is formed

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15-10-2012 дата публикации

Automated Ultrasonic Digital Board for Buffering and Transmission of Multi Channel, High Speed ADC Data

Номер: KR101189907B1
Принадлежит: 한국수력원자력 주식회사

본 발명은 자동 초음파 검사 시스템에 있어 고성능의 FPGA, DDR2 메모리, 아날로그-디지털 변환기(A/D 변환기)를 이용하여 다채널(최대 8채널) 12비트, 200MHz의 초음파 데이터 샘플링이 가능하며, 내부적인 디지털 필터링, 실시간 엔코더 데이터 감시, 호스트 PC와의 이더넷을 통한 데이터 전송을 동시에 병렬로 처리할 수 있는 디지털 보드를 제공한다. 본 발명의 디지털 보드는, 아날로그 초음파 신호의 입력 커넥터, 차동 전치증폭기, 매우 높은 단위 대역폭(-3dB: 2.2GHz)을 갖는 연산증폭기(1)를 사용하여 외부 노이즈 제거와 아날로그 초음파 신호의 왜곡을 방지하며, 입력된 아날로그 초음파 신호를 디지털 신호로 변환하는 A/D 변환기(2), A/D 변환기와의 FPGA 인터페이스(3), A/D 변환된 디지털 신호를 수신하는 FPGA의 입력단(4), 디지털 신호를 실시간으로 저장하기 위한 FPGA와 메모리 인터페이스(5), 저장된 신호를 PC로 전송하기 위한 FPGA와 CPU와의 인터페이스(6)를 통해 12비트, 200MHz의 데이터를 최대 8채널까지 동시에 샘플링하고, 내부적인 디지털 필터링과 실시간 엔코더 데이터 감시, PC와의 데이터 전송을 동시에 병렬로 처리할 수 있도록 내부 로직을 설계함으로써 구성된다. 그리고, 이러한 디지털 보드는, 고성능의 FPGA, 고속DDR2 메모리, A/D 변환기, 32비트 RISC CPU를 구성하는데 사용된다. The present invention is capable of multi-channel (up to 8 channels) 12-bit, 200 MHz ultrasonic data sampling using high-performance FPGA, DDR2 memory, analog-to-digital converter (A / D converter) in the automatic ultrasonic inspection system. It offers digital boards that can handle digital filtering, real-time encoder data monitoring, and data transfer over Ethernet with a host PC in parallel. The digital board of the present invention uses an input connector of an analog ultrasonic signal, a differential preamplifier, and an operational amplifier 1 having a very high unit bandwidth (-3 dB: 2.2 GHz) to remove external noise and prevent distortion of the analog ultrasonic signal. An A / D converter 2 for converting the input analog ultrasonic signal into a digital signal, an FPGA interface 3 with the A / D converter, an input terminal 4 of the FPGA for receiving the A / D converted digital signal, Simultaneously sample up to eight channels of 12-bit, 200 MHz data through an FPGA and memory interface (5) for storing digital signals in real time, and an interface between the FPGA and CPU (6) for transferring stored signals to a PC. It is configured by designing internal logic to simultaneously process in-digital filtering, real-time encoder data monitoring, and ...

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02-06-2008 дата публикации

Remote-controlled guide system for robot repairing crdm nozzle of nuclear reactor head

Номер: KR100834686B1

원자로 헤드 관통관 보수 로봇용 원격 제어 가이드 시스템은, 수평 가이드, 수직 가이드, 그리고 제어부를 포함한다. 수평 가이드는 원자로 헤드 안착대의 내부로 삽입될 수 있도록 형성되며, 적어도 하나의 베이스, 상기 베이스 상에 설치되는 수평 가이드 레일, 그리고 상기 원자로 헤드 안착대의 내벽을 지지하는 원자로 헤드 안착대 내벽 지지부를 포함한다. 수직 가이드는 원자로 헤드 관통관을 보수하는 보수 로봇을 고정하는 로봇 고정부, 제1 구동장치를 포함하며 상기 제1 구동장치의 작동에 의해 상기 수평 가이드 레일 상을 이동할 수 있도록 형성되는 대차, 그리고 상기 대차에 고정되며 상기 로봇 고정부를 수직 방향으로 이동시키는 제2 구동장치를 가지는 수직 이송 구동부를 포함한다. 제어부는 상기 대차 및 상기 로봇 고정부의 위치가 조절될 수 있도록 상기 제1 및 제2 구동장치의 작동을 제어한다. 원자로 헤드 관통관 보수 로봇이 원격 제어를 통해 원자로 헤드 안착에 안으로 수평 이송시켜 주고, 손상된 관통관까지 용접 보수 장치가 도달할 수 있도록 수직 이송시켜 주고, 보수 로봇이 용접 보수 작업을 원활히 수행할 수 있도록 견고한 지지를 제공함으로써 작업자의 방사선 피복을 최소화하고 원자로 헤드 관통관의 손상을 원격으로 보수할 수 있다. The remote control guide system for the reactor head through-tube maintenance robot includes a horizontal guide, a vertical guide, and a control unit. The horizontal guide is formed to be inserted into the reactor head restraint, and includes at least one base, a horizontal guide rail installed on the base, and an inner wall support of the reactor head restraint supporting an inner wall of the reactor head restraint. . The vertical guide includes a robot fixing part for fixing a repair robot for repairing the reactor head through tube, a first driving device, and a bogie configured to move on the horizontal guide rail by operation of the first driving device, and And a vertical conveying drive unit fixed to the cart and having a second driving device for moving the robot fixing unit in the vertical direction. The control unit controls the operation of the first and second driving devices so that the position of the bogie and the robot fixing part can be adjusted. Reactor head through-tube repair The robot can remotely transport the reactor head into the reactor seat through the remote control, vertically transport the damaged repair pipe to reach the damaged through-pipe, and allow the repair robot to perform the welding repair work smoothly. Providing robust support minimizes operator radiation coverage and remotely repairs damage to ...

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18-12-2019 дата публикации

System of acoustic leak monitoring of npp pipeline

Номер: RU2709474C1

FIELD: monitoring and measuring equipment. SUBSTANCE: invention relates to control of tightness of equipment of potentially hazardous industrial facilities and, in particular, can be used for detection, localization and determination of leakage value of heat carrier from pipelines of the first circuit of water-and-water power reactors (WWPR). System of acoustic monitoring of pipeline of nuclear power plant (NPP) includes acoustic sensors, switching boxes connected to acoustic sensors, software and hardware complex, which includes a computing device, amplifying-converting modules and a power supply, analogue communication lines connecting switching boxes with a software and hardware system. Amplification-converting modules are combined into signal processing unit. Outputs of switching boxes are connected to input of signal processing unit by means of analogue communication lines passing through sealed passage of sealed shell of reactor plant of NPP. Output of the signal processing unit is connected to the input of the computing device through a digital communication line, and the power supply is connected to the signal processing unit through a power line. EFFECT: invention widens the dynamic range of controlled leaks towards control of small leaks. 1 cl, 1 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 709 474 C1 (51) МПК G21C 17/017 (2006.01) F17D 5/02 (2006.01) G01M 3/04 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 17/017 (2019.08); F17D 5/02 (2019.08); G01M 3/04 (2019.08) (21)(22) Заявка: 2019127889, 04.09.2019 (24) Дата начала отсчета срока действия патента: Дата регистрации: 18.12.2019 (45) Опубликовано: 18.12.2019 Бюл. № 35 Адрес для переписки: 121165, Москва, Г-165, а/я 15, ЮСТИС (73) Патентообладатель(и): Акционерное общество "Научно-технический центр "Диапром" (RU) C 1 2 7 0 9 4 7 4 R U (54) Система акустического контроля течи трубопровода АЭС (57) Реферат: Изобретение относится к контролю ...

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05-01-2011 дата публикации

Loss-of-coolant accident test system and method of controlling loss-of-coolant accident test system

Номер: KR101005711B1
Автор: 김병덕, 김재형, 송치성
Принадлежит: 한국기계연구원

PURPOSE: A LOCA(Loss Of Coolant Accident) test system and a control method thereof are provided to reduce manufacturing costs by excluding an additional device to measure the density of boron solutions. CONSTITUTION: A supply pump(120) supplies boron solutions. A LOCA test chamber(140) mixes boron solutions and steam. A boron circulation pump(150) circulates boron solutions flown from the LOCA test chamber. A boron storage unit(170) stores boron solutions supplied from the boron circulation pump. A boron supplement unit(180) supplements boron solutions stored in the boron storage unit with boron. A controller controls the supply pump and the boron supplement unit.

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06-02-2015 дата публикации

moving platform inspecting and maintaining apparatus for nuclear reactor

Номер: KR101488712B1
Принадлежит: 한전케이피에스 주식회사

The present invention relates to a moving platform of an inspection and maintenance device for a reactor head, comprising: an x-axis support unit (10) which is installed to be rotated on the upper top surface of a bioshield (201) installed in a reactor head (200) and move a z-axis support unit (40) installed on the top surface thereof forward/backward in an x-axis direction; a rotation axis support unit (20) which includes at least two or more axes, meets the x-axis support unit (10) at the center thereof and is extended to the upper top surface of the bioshield (201) in a radius direction; a rotation roller (30) which is attached to the ends of the x-axis support unit (10) and the rotation axis support unit (20) to be rotated along the upper top surface of the bioshield (201); the z-axis support unit (40) which is installed on the top surface of the x-axis support unit (10) to vertically move an inspection or maintenance device (300); and an x-axis actuator (50) which is installed on the other end of the x-axis support unit (10) to move the z-axis support unit (40) forward/backward along an x-axis. The moving platform is capable of: performing various works by freely detaching/attaching the non-destructive inspection and maintenance system in the reactor head; being applied to various reactor heads by freely adjusting lengths of the support axes: minimizing workers by automatically moving the inspection and maintenance system in a high radioactivity area; easily disassembling/assembling equipment; and minimizing workers by allowing the workers to freely move/install the equipment having the small weight, thereby improving efficiency in inspection and maintenance.

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25-11-2014 дата публикации

Jig for fracture thoughness test and apparatus for fracture thoughness test using the same

Номер: KR101465388B1
Автор: 김익현, 석창성
Принадлежит: 성균관대학교산학협력단

The present invention relates to a jig for a fracture toughness test capable of applying a stable load to a test piece and inducing to occur fracture in a predetermined site, and an apparatus for fracture toughness test using the same. The provided jig for a fracture toughness test comprises: a thread pipe test piece which is formed with a breaking portion and formed with a groove to be inwardly recessed in the circumferential direction; a holder which is formed in a pair to be mounted at both ends of the thread pipe test piece to receive the groove and formed with a through groove having to be inserted with the test piece; a ring member mounted on the groove; and a locking member which is interposed between the ring member and the holder to prevent separation of the ring member.

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18-04-2017 дата публикации

Circumferential sampling tool having multiple sample cutters and method of obtaining samples

Номер: KR101727966B1

관의 내벽으로부터 샘플들을 얻기 위한 원주방향 샘플링 도구는, 원통형 몸체, 이 원통형 몸체에 배치되는 샤프트, 제1 커터, 이 제1 커터에 경사지게 배치되는 제2 커터, 제3 커터, 이 제3 커터에 경사지게 배치되는 제4 커터를 갖는다. 제1, 제2, 제3 및 제4 커터들은 함께 회전하기 위하여 샤프트에 작동 가능하게 연결된다. 각각의 커터는 관으로부터 샘플들을 얻기 위해서 샤프트의 회전에 따라 퇴축 위치와 연장 위치 사이에서 반경방향으로 이동가능하다. 관의 내벽으로부터 샘플들을 얻기 위한 방법도 개시된다. A circumferential sampling tool for obtaining samples from the inner wall of the tube comprises a cylindrical body, a shaft disposed in the cylindrical body, a first cutter, a second cutter disposed obliquely to the first cutter, a third cutter, And a fourth cutter disposed obliquely. The first, second, third and fourth cutters are operatively connected to the shaft for rotation together. Each cutter is movable in the radial direction between the retracted position and the extended position in accordance with the rotation of the shaft to obtain samples from the tube. A method for obtaining samples from the inner wall of a tube is also disclosed.

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27-03-2020 дата публикации

Remote diagnosis system for spary nozzle in containment building

Номер: KR102094364B1
Автор: 장유현, 허민웅
Принадлежит: 한국수력원자력 주식회사

여러 개 살수 노즐의 작동 상태를 동시에 원격으로 점검할 수 있는 격납 건물의 살수 노즐 원격 진단 시스템을 제공한다. 격납 건물의 살수 노즐 원격 진단 시스템은 살수 노즐의 온도 변화를 원격으로 검출하는 열화상 카메라와, 열화상 카메라가 취득한 열화상 데이터로부터 살수 노즐의 온도 변화량을 측정하고, 살수 노즐의 유동 임계압력을 계산하며, 살수 노즐의 온도 변화를 예측하고, 살수 노즐의 유동량을 산출하여 살수 노즐의 작동 상태 진단을 위한 정보를 제공하는 전자 계산부를 포함한다. Provides a remote diagnosis system for a sprinkling nozzle in a containment building that can remotely check the operation status of several sprinkling nozzles simultaneously. The sprinkling nozzle remote diagnosis system in the containment building measures the temperature change amount of the sprinkling nozzle from the thermal imaging camera that remotely detects the temperature change of the sprinkling nozzle, and the thermal image data acquired by the thermal imaging camera, and calculates the critical flow rate of the sprinkling nozzle. It includes an electronic calculation unit that predicts the temperature change of the sprinkling nozzle, calculates the flow rate of the sprinkling nozzle, and provides information for diagnosing the operating state of the sprinkling nozzle.

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12-05-2020 дата публикации

Method for evaluating pipeline thinning rate

Номер: CN111141244A

本发明涉及一种评估管道减薄速率的方法,用于对作为评估对象的管道或管段的减薄速率进行评估,评估管道减薄速率的方法为:首先将评估对象划分为若干分析单元,再分别计算各分析单元的减薄速率,最后将计算出的各分析单元的减薄速率的最大值作为评估对象的减薄速率。计算分析单元的减薄速率的方法为:检测获得分析单元各处的多个厚度值,取分析单元的名义厚度和检测到的最大厚度中的较大者作为原始厚度,则分析单元的减薄速率为原始厚度和检测到的最小厚度的差值与间隔时间的比值。本发明能够较为准确地计算管道减薄速率,避免了传统计算过程中出现的较大计算误差,为管道寿命预测提供科学的依据和方法。

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24-07-2015 дата публикации

Inspection device of penetration for reactor upper head

Номер: KR101539538B1
Автор: 김윤원
Принадлежит: 한전케이피에스 주식회사

The present invention relates to a device for inspecting a penetrating pipe of a reactor upper head. In particular, the device of the present invention comprises: an end-effector (100) placed on the bottom of a penetrating pipe (P) of a reactor upper head; a camera (110) placed in the center of the end-effector (100) for checking the center of the penetrating pipe (P); a gripper (120) placed on both ends of the top of the end-effector (100) for fixating the penetrating pipe (P); an elevation operating unit (130) placed on the end-effector (100) for elevating the gripper (120); an ultrasonic probe placed on the elevation operating unit (130) for inspecting the penetrating pipe (P); and an operating unit (150) for moving the ultrasonic probe. The center of the end-effector (100) and the center of the penetrating pipe (P) can be made to accurately match each other by the gripper (120) placed on both sides of the end-effector (100), and the degree of precision of ultrasonic inspection data can be improved. As a plurality of motors is installed for inspection, operation, and function check of the end-effector (100), the end-effector (100) can separately inspect, operate, and check the functions of the penetrating pipe (P), enhancing the convenience of work and reliability of the inspection.

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04-03-2020 дата публикации

Foreign material shooting and removal for steam generators of nuclear power plants

Номер: KR102084075B1
Принадлежит: 앤스코 주식회사

Disclosed is a foreign substance photographing and removing device for a steam generator at a nuclear power plant and, more specifically, to a disclosed foreign substance photographing and removing device for a steam generator at a nuclear power plant, capable of photographing and removing a foreign substance or sludge in a gap of a heat transfer tube by flowing into the gap of the heat transfer tube through a driving drum of a transfer robot moved along a ring-shaped inner wall of a steam generator. The foreign substance photographing and removing device includes: a strip made of a flexible metal band; and a probe combined with a tip of the strip. The foreign substance photographing and removing device also includes: a relative gear part provided above the strip to be interlocked with gear teeth formed on the outer edge surface of the driving drum which is rotated normally or reversely; a first electric wire placement part provided in the middle of the strip to place an electric wire in a longitudinal direction of the strip; and a second electric wire placement part provided below the strip to place an electric wire in a longitudinal direction of the strip. The foreign substance photographing and removing device also includes: first and second probing cameras installed in the probe at different angles to photograph front and lower parts; and a gripper installed to remove a foreign substance by gripping the foreign substance.

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26-09-2012 дата публикации

Tubular pipe for transporting liquid sodium

Номер: CN102696072A
Принадлежит: A HAIFA

本发明涉及可以抑制钠泄漏到管道外的用于输送液态钠的管状管道(10)。该管道包括内部由内层覆盖的管道体(20),内层包括:由陶瓷或金属或金属合金制成的第一连续层(40),用于与由管状管道输送的液态钠接触;以及在管道体与所述第一陶瓷层之间由反应材料制成的中间层(50),该中间层(50)在与液态钠接触时,转化为电导率与反应材料不同的改性材料。

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25-02-2015 дата публикации

An inspecting robot arrangement device

Номер: KR101496020B1
Принадлежит: 한국수력원자력 주식회사

본 발명은 원자로에 구비된 칼란드리아 관에 삽입되는 검사로봇의 정렬을 위한 검사로봇 정렬장치에 관한 것으로, 더욱 상세하게는 상기 검사로봇에 구비되어 레이저를 발광하는 레이저발광부; 상기 검사로봇의 단부 외측면에 형성된 연결판; 상기 연결판의 단부에 구비되어 상기 레이저발광부를 통해 발광된 레이저가 일정각도 꺾여져 상기 칼란드리아 관 내벽으로 반사되도록 하는 반사부; 및 상기 검사로봇에 구비되어 상기 반사부를 통해 반사된 레이저가 수광되는 레이저수광부; 상기 칼란드리아 관 내벽에서 반사되는 레이저를 스캔하는 스캔부; 및 상기 스캔부를 통해 스캔정보를 입력받아 검사로봇의 위치를 조절하는 제어부;를 포함하는 검사로봇 정렬장치에 관한 것이다. 본 발명은 검사로봇 정렬장치는 칼란드리아 관 내벽에서 반사되는 레이저의 반사과정(스캔정보)을 이용하여 검사로봇의 위치가 조절되도록 함으로써 칼란드리아 관 내부 벽면에 접촉되지 않은 상태로 검사로봇이 칼란드리아 관 내부에 삽입되어 기기에 대한 검사를 수행할 수 있게 하는 효과가 있다. 또한 칼란드리아 관과 검사로봇의 접촉으로 인한 칼란드리아 관 내벽과 검사로봇의 파손을 방지하는 효과도 있다. The present invention relates to an inspection robot alignment apparatus for aligning an inspection robot inserted into a calandria tube provided in a reactor, and more particularly, A connection plate formed on an outer side surface of the end portion of the inspection robot; A reflector provided at an end of the coupling plate to reflect the laser emitted through the laser emitting unit to an inner wall of the calandria tube by being bent at a predetermined angle; And a laser light receiving unit provided in the inspection robot and receiving a laser reflected through the reflection unit; A scan unit for scanning a laser beam reflected from the inner wall of the calandria tube; And a controller for receiving the scan information through the scan unit and adjusting the position of the inspection robot. In the inspection robot alignment apparatus, the position of the inspection robot is adjusted by using the reflection process (scan information) of the laser reflected from the inner wall of the calandria tube, so that the inspection robot is not in contact with the inner wall of the calandria tube, It is possible to inspect the apparatus by inserting it into the tube. It also has the effect of preventing damage to the inner wall of the calandria tube and the inspection robot caused by contact between the calandria tube and the inspection robot.

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28-06-2012 дата публикации

Sensor guiding apparatus for the inspection of inner part of helical type tube

Номер: KR101160662B1
Автор: 서용칠
Принадлежит: 한국원자력연구원

본 발명은 원자로의 나선형 증기발생기 세관에 삽입되되 상기 나선형 증기발생기 세관의 형상에 대응되게 변형되도록 유연하게 형성된 플렉시블 호스와, 상기 플렉시블 호스의 외측에 삽입되어 상기 플렉시블 호스를 지지하되, 상기 증기발생기 세관의 내면에 접하면서 상기 플렉시블 호스가 상기 증기발생기의 세관에 삽입되는 것을 안내하는 안내부 및 상기 플렉시블 호스를 감싸며 상기 안내부와 연결되게 설치되어 상기 증기발생기 세관 내부에서 초음파를 발생시키는 초음파 가진기가 포함되고, 상기 안내부는 상기 플렉시블 호스의 외면에 삽입되는 안내본체와, 상기 안내본체의 외면에 설치되어 상기 플렉시블 호스가 상기 증기발생기 세관의 내부로 삽입될 때 상기 증기발생기 세관의 내면과 접하면서 회전하는 롤링부재가 포함된 것을 특징으로 하는 나선형 튜브 내면 검사용 센서 안내장치에 관한 것이다. 이에, 본 발명은 플렉시블 호스가 증기발생기 세관의 형상에 대응되게 유연하게 휘어지면서 삽입됨은 물론, 플렉시블 호스에 설치된 안내부의 외면에 설치된 다수의 롤링부재가 회전함에 따라 플렉시블 호스를 삽입할 때 가해지는 힘이 최소화되고 플렉시블 호스와 증기발생기 세관 사이에 마찰이 발생하는 것을 최소화하여 플렉시블 호스에 설치된 초음파 가진기의 삽입을 용이하게 할 수 있는 효과가 있다. The present invention is inserted into the helical steam generator tubules of the nuclear reactor and flexible flexible formed to deform to correspond to the shape of the helical steam generator tubules, and inserted into the outer side of the flexible hose to support the flexible hose, the steam generator tubules A guide part which guides the flexible hose to be inserted into the tubule of the steam generator while being in contact with the inner surface of the steam generator; The guide portion is inserted into an outer surface of the flexible hose and the guide body is installed on the outer surface of the guide body to rotate while contacting the inner surface of the steam generator customs when the flexible hose is inserted into the steam generator customs Characterized in that a rolling member is included It relates to a sensor guide device for inspecting the inner surface of the spiral tube. Therefore, in the present invention, the flexible hose is inserted while flexibly flexed to correspond to the shape of the steam generator tubule, as well as the force applied when the flexible hose is inserted as the plurality of rolling members installed on the outer surface of the guide part installed in the flexible hose rotate. This has the effect of minimizing and minimizing the friction between the flexible hose and the steam ...

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11-03-2005 дата публикации

Reference electrode for measuring the potentials of underground metallic structures

Номер: KR200377964Y1
Принадлежит: 한국전기연구원

본 고안은 기준전극에 적용되는 다공성 세라믹팁을 테이퍼 형상으로 하여 하부캡과의 결합에 의한 밀폐도가 향상되도록 함으로써, 황산동 용액의 불필요한 누출을 방지하도록 하는 지중 금속 구조물의 전위 측정용 기준전극 구조를 제공한다. 이를 위해 본 고안은 황산동 용액을 수용하는 수용공간이 형성된 케이싱과, 상기 케이싱의 상부에 결합되어 구리전극을 고정시키는 상부 실링, 그 내부에 천공부가 형성되고서, 상기 케이싱의 하부에 결합되는 하부 캡 및, 상기 하부캡의 천공부에 결합되어 황산동 용액이 소량 누출되도록 함과 더불어, 상기 천공부의 밀폐를 위해 테이퍼 형상으로 이루어진 세라믹팁으로 구성된 것을 특징으로 한다. The present invention has a tapered shape of the porous ceramic tip applied to the reference electrode to improve the sealing by the coupling with the lower cap, thereby preventing the reference leakage structure of the underground metal structure to prevent unnecessary leakage of copper sulfate solution to provide. To this end, the present invention provides a casing having an accommodating space for accommodating a copper sulfate solution, an upper seal coupled to an upper portion of the casing to fix a copper electrode, a perforated portion formed therein, and a lower cap coupled to a lower portion of the casing; It is coupled to the perforated portion of the lower cap to allow a small amount of copper sulfate solution leak, characterized in that consisting of a ceramic tip made of a tapered shape for sealing the perforated portion.

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11-10-2016 дата публикации

Method of modeling steam generator and processing steam generator tube data of nuclear power plant

Номер: KR101665157B1
Автор: 퀴 브이 르

원자로의 증기 발생기의 튜브들을 검사하는 개선된 방법은 증기 발생기를 모델링하는 단계, 및 추가의 분석이 요구되는지를 판정하기 위해 와전류 센서로부터의 튜브의 신호들을 모델의 양상들과 비교하는 단계를 포함한다. 모델은 증기 발생기로부터 수집된 과거 데이터에 기초하는 특정 튜브들의 특정 ROI들(regions of interest)에 관한 예외 데이터를 유리하게 포함할 수 있다. An improved method of inspecting the tubes of a reactor steam generator includes modeling the steam generator and comparing the signals of the tube from the eddy current sensor with aspects of the model to determine if further analysis is required . The model may advantageously include exception data relating to particular regions of interest of particular tubes based on historical data collected from the steam generator.

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21-02-2020 дата публикации

Nuclear power plant pipeline thermal fatigue monitoring system

Номер: CN110828011A

本发明公开了一种核电厂管道热疲劳监测系统,包括安装于安全壳内一回路管道上的疲劳监测传感器组件、安装于安全壳内的数据采集单元、安装于安全壳外的光电转换单元和监视与分析评估单元;所述疲劳监测传感器组件包括热电偶、套设在部分所述热电偶上的金属编织软管、将所述热电偶安装在管道上的安装支架以及将热电偶固定在所述安装支架上的滑块;所述数据采集单元包括环境传感器,所述数据采集单元用于接收疲劳监测传感器组件及环境传感器所测得的模拟信号,并将其转换为数字信号后输出;所述光电转换单元用于接收所述数字信号并将其转化为光信号,输送给监视与分析评估单元;所述监视与分析评估单元用于接收所述光信号并进行热疲劳的监视和分析评估。

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04-01-2021 дата публикации

Inspection device for steam generator

Номер: KR102197774B1
Принадлежит: 두산중공업 주식회사

본 발명은 전열관다발 틈새의 이물질 유무 등을 검사할 수 있는 증기발생기 검사장치에 관한 것으로, 증기발생기의 핸드홀을 통해 상기 증기발생기의 외측에 설치되는 프레임부와, 상기 핸드홀을 통해 상기 증기발생기의 내부로 일부가 돌출되도록 상기 프레임부에 설치되는 레일가이드부와, 상기 레일가이드부를 통해 상기 증기발생기의 내부에 배치되는 레일부와, 상기 레일부에 이동 가능하게 설치되며 검사용 카메라가 구비되는 검사부 및 상기 레일부와 검사부를 구동하기 위한 구동부를 포함하는, 증기발생기 검사장치를 제공한다. The present invention relates to a steam generator inspection device capable of inspecting the presence or absence of foreign substances in a gap in a heat transfer pipe bundle, and a frame portion installed outside the steam generator through a hand hole of the steam generator, and the steam generator through the hand hole. A rail guide part installed on the frame part so as to protrude a part into the inside of the rail guide part, a rail part disposed inside the steam generator through the rail guide part, and movably installed in the rail part and equipped with an inspection camera. It provides a steam generator inspection apparatus comprising an inspection unit and a driving unit for driving the rail unit and the inspection unit.

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