УСТРОЙСТВО ДЛЯ ИЗВЛЕЧЕНИЯ УПАВШИХ ПРЕДМЕТОВ ЯДЕРНОГО РЕАКТОРА

FIELD: nuclear equipment.SUBSTANCE: invention relates to atomic engineering. Device for removing fallen objects of a nuclear reactor comprises a movable platform with a lifting machine, drive, vertical hollow rod coupled with a gripper comprises gripping claws connected with swivel levers by a hinge joint. Device additionally contains a support frame with a ropes-rods equipped with a drive which is connected in the upper part to the lifting machine, and in the lower part – to a fixed hollow section of a telescopic bar. Movable section of the bar is connected to the rope-rod of its movement along the vertical line and in the lower part is connected to the gripping device, which includes a hollow body with a slot, equipped in its lower part with common axis of two levers and movable weight connected with a movable load by the rope-rod, which in lower part is made with two horizontal axes, arranged in slots of two levers on common axis and turning levers at moving the movable load. Gripping claws form a hinge joint with the levers and at the ends they have connection with the ropes-rods for their rotation.EFFECT: invention makes it possible to adjust the gripping position of the device excluding damage to an object at the time of engagement.1 cl, 6 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 683 581 C2 (51) МПК G21C 19/10 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/10 (2018.08) (21)(22) Заявка: 2016151925, 28.12.2016 (24) Дата начала отсчета срока действия патента: Дата регистрации: 29.03.2019 (43) Дата публикации заявки: 02.07.2018 Бюл. № 19 (45) Опубликовано: 29.03.2019 Бюл. № 10 2 6 8 3 5 8 1 R U (56) Список документов, цитированных в отчете о поиске: RU 2418329 C1, 10.05.2011. SU 638540 A1, 25.12.1978. RU 2066488 C1, 10.09.1996. US 3945514 A1, 23.03.1976. FR 2905030 A1, 22.02.2008. (54) УСТРОЙСТВО ДЛЯ ИЗВЛЕЧЕНИЯ УПАВШИХ ПРЕДМЕТОВ ЯДЕРНОГО РЕАКТОРА (57) Реферат: Изобретение относится к атомному ...

Манипулятор для сборки пучка тепловыделяющих элементов

Изобретение относится к области ядерной энергетики, в частности к манипуляторам для сборки пучка тепловыделяющих элементов. Манипулятор содержит: верхнюю раму, включающую первые направляющие и первое быстроразъемное соединение; нижнюю раму, включающую вторые направляющие, второе быстроразъемное соединение и первый универсальный привод. Манипулятор также содержит модуль вертикального перемещения, выполненный с возможностью установки на верхней раме и возможностью стыковки с тепловыделяющим элементом. Узел подачи тепловыделяющих элементов выполнен с возможностью установки на верхней части нижней рамы и с возможностью последовательного приема тепловыделяющих элементов. Хомут установлен в нижней части нижней рамы и выполнен с возможностью фиксации пучка тепловыделяющих элементов. Толкатель выполнен с возможностью установки на верхней части нижней рамы и с возможностью перемещения тепловыделяющих элементов из узла подачи тепловыделяющих элементов в хомут. Датчик выполнен с возможностью установки ...

Программно-аппаратный комплекс выявления опасного приближения рабочей штанги к стенкам бассейна ядерного топлива на основе видеонаблюдения

Изобретение относится к области обработки видеопотоков. Технический результат заключается в повышении точности и надежности выявления опасного приближения рабочей штанги к стенкам бассейна в процессе перегрузки ядерного топлива. Программно-аппаратный комплекс включает взаимодействующие между собой модуль настройки сервера, модуль настройки приложения, модуль визуализации видеонаблюдения, модуль управления видеокамерами, причем дополнительно содержит модуль видеоаналитки, который системно связан с модулем управления интегральным алгоритмом, при этом последний взаимосвязан с модулем управления алгоритмом аналитики видеонаблюдения методом распознавания цветовых пятен, модулем управления алгоритмом аналитики видеонаблюдения методом граней, основанным на контурном анализе и методах работы с контурами, модулем управления алгоритмом обученной нейронной сети, а также соединен с системным модулем управления машиной перегрузочной. 1 ил.

Приспособление для извлечения трубы обсадной разгрузочно-загрузочной машины

FIELD: machine building. SUBSTANCE: invention relates to nuclear engineering. Device for extraction of pipe of casing unloading-loading machine (ULM) includes connected between axes mandrel and bracket, stops installed on bracket, magnets. Mandrel structure is made with possibility of rotation on axle by one part of complex spatial geometrical shape, obtained as a result of machining of billet in two projections by intersection of two solid cylindrical surfaces made in one projection with cylindrical surface. In smooth holes of the mandrel the magnets are installed at different polarity. Bracket design is made in the form of a key and is equipped with a ledge with a recess for arrangement and fixation of stops in it. Device is configured for free movement inside casing pipe in fixed position of mandrel relative to bracket and possibility of lock release and turning mandrel relative to bracket before engagement with casing pipe only with simultaneous action of magnetic forces on all stops. EFFECT: invention allows automatic process of engagement of the appliance with the casing of the transitional unloading-loading machine guide when it is removed from the pipe. 7 cl, 20 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 717 964 C1 (51) МПК G21C 19/10 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/10 (2020.01) (21)(22) Заявка: 2019131300, 02.10.2019 (24) Дата начала отсчета срока действия патента: Дата регистрации: 27.03.2020 (45) Опубликовано: 27.03.2020 Бюл. № 9 2 7 1 7 9 6 4 R U (56) Список документов, цитированных в отчете о поиске: RU 2687244 C1, 08.05.2019. RU 2484240 C1, 10.06.2013. RU 2167273 C1, 20.05.2001. RU 2569336 C1, 20.11.2015. US 20131077124 A1, 11.07.2013. (54) Приспособление для извлечения трубы обсадной разгрузочно-загрузочной машины (57) Реферат: Изобретение относится к области атомного выполнена в форме ключа и оснащена выступом машиностроения. Приспособление для извлечения с выемкой ...

УСТРОЙСТВО ДЛЯ КОНТРОЛЯ ТЕПЛОВЫДЕЛЯЮЩИХ СБОРОК С ЯДЕРНЫМ ТОПЛИВОМ

Группа изобретений относится к области инспекционного контроля тепловыделяющих сборок (ТВС). Оборудование для контроля ТВС с ядерным топливом содержит контрольное оборудование с по меньшей мере одной видеокамерой. Оборудование содержит: контрольную стойку, разработанную для проведения выдвижного движения в бассейн топлива, которая на одном конце снабжена соединительным средством, позиционируемый механизм перемещения, разработанный для соединения с указанным соединительным средством контрольной стойки. Позиционируемый механизм перемещения создан для изменения положения контрольной стойки в бассейне топлива. Контрольная стойка снабжена подвижным захватом, предназначенным для захватывания ТВС, когда данный захват расположен подвижно в контрольной стойке и предназначен для подъема ТВС со стеллажа хранения топлива бассейна топлива и для втягивания данной ТВС в контрольную стойку. Контрольная стойка оснащена одной видеокамерой для контроля поверхности ТВС, одним измерительным зондом. Также описан ...

Захватное устройство для элементов активной зоны ядерного реактора

DEVICE FOR CHECKING THE DISCONNECTION OF NUCLEAR REACTOR CONTROL CLUSTERS

Brennstoffelement-Kette

Greifervorrichtung an einer Lademaschine fuer Kernreaktoren

Transfervorrichtung für den Transfer von Brennelementen

Es handelt sich um eine Transfervorrichtung (6) für den Transfer von Brennelementen (5) zwischen einem oberen Becken (3) und einem unteren Becken (4) einer kerntechnischen Anlage, insbesondere einem oberen Becken innerhalb eines Reaktorgebäudes (1) und einem unteren Becken eines Brennelementelagers (2), mit einem das obere und das untere Becken (3, 4) verbindenden und schräg zur Vertikalen verlaufenden Transferrohr (12), einem oder mehreren Transferkörben (11), in welche jeweils ein oder mehrere Brennelemente (5) für den Transfer durch das Transferrohr (12) einsetzbar sind, einer oberen Umladeeinrichtung (21) im oberen Becken (3) zum Beladen und/oder Entladen der Transferkörbe (12) mit Brennelementen (5) und/oder einer unteren Umladeeinrichtung (22) im unteren Becken zum Beladen und/oder Entladen der Transferkörbe (12) mit Brennelementen (5), Diese Vorrichtung ist dadurch gekennzeichnet, dass in die obere Umladeeinrichtung (21) und/oder die untere Umladeeinrichtung (22) jeweils zwei Transferkörbe ...

Handhabungseinrichtung und Verfahren zur Handhabung reaktorinterner Geräte

LADUNG EINES KERNREAKTORS.

MODERATORAUFBAU FUER ATOMKERNREAKTOR

GRIPPING DEVICE

... 1332408 Gripping devices for fuel element and control rod holders LICENTIA PATENTVERWALTUNGS GmbH 19 April 1971 [15 April 1970] 26442/71 Heading B8H A gripping device is provided with an insert 12 in a slot 7 to enable it to selectively pick up holders for fuel elements or control rods in a nuclear reactor. The device also comprises a jaw-shaped aperture 5 and a rotatable gripper hook 3. The insert 12 can be positioned as shown in Fig. 3 with the prongs 13, 14 facing outwardly when only control rod holders can be picked up since the thicker fuel element holders cannot enter the gap between the prongs 13, 14 and hence cannot be engaged by the hook 3. With the insert 12 in its alternative position (Figs. 1 and 4) only the fuel element holders can be picked up since the insert 12 prevents the control rod holders from getting far enough into the slot 7 to be engaged by the hook 3. The inset 12 may be replaced by one allowing more than two shapes to be selectively lifted.

Grabs for handling nuclear fuel elements

... 1,088,969. Lifting nuclear fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. Aug. 5, 1966 [Aug. 13, 1965], No. 35265/66. Heading B8H. To remove a nuclear fuel element 80, Fig. 4, from a hollow nozzle 81 where it is held by balls 83 which are pushed outwards by a spring-loaded sleeve 84 a grab 1 is lowered into the hollow head of the element and latched thereto by balls 34. The balls 34 are urged outwards by a slide - block 29 which is moved up the grab by a screw 18 turned in a fixed nut 19 by an electric motor 9 and a sleeve 12. When a rod 35, which moves with the slide block 29, closes contacts 36 the motor 9 stops. After a time delay a second motor 66 is energized and pushes arms 69, 70, Fig. 4, out of slits 79, 80, Fig. 1, by rotating a differential housing 50. The housing 50 is prevented from further rotation by the arms 69, 70 when the latter are fully extended. Continued rotation of the motor 66 causes rotation of a screw 42 in a nut 43, through the differential gearing, which raises ...

Improvements in or relating to couplings

... 963,955. Controlling nuclear reactors. GENERAL DYNAMICS CORPORATION. Oct. 17, 1962 [Nov. 7, 1961], No. 39352/62. Heading G6C. [Also in Divisions E2 and F2] A coupling mechanism for connecting a nuclear reactor control rod 25 having an enlarged head 31 forming a male coupling member with an elongated driving shaft 35 having a lengthwise bore 37 comprises a female coupling member 61 rotatably attached to one end of the shaft 35 and means 65 accessible through the bore 37 for releasably locking the member 61 to the shaft 35 to prevent rotation therebetween, the member 61 including a bayonet-type socket 101 which receives the head 31 of the rod 25 and is so shaped that rotation of the socket 101 relative to the head 31, when this is fully inserted in the socket, locks the rod 25 to the shaft 35. The head 31 is in the form of a sphere having portions cut away to provide a cruciform cross-section and is inserted through a tapered opening in the base of the coupling member 61 towards a receiving ...

Gripping apparatus including a television camera

... 1,058,851. Lifting nuclear fuel elements. SOC. ALSACIENNE DE CONSTRUCTIONS ATOMIQUES DE TELE-COMMUNICATIONS ET D'ELECTRONIQUE " ALCATEL," and SOC. DE TRANSACTIONS COMMERCIALES ET INDUSTRIELLES ENTRE LA FRANCE ET L'ALLEMAGNE. April 3, 1964 [April 5, 1963], No. 13847/64. Heading B8H. [Also in Divisions G2 and H4] A gripping device for handling, e.g. a fuel element A in a nuclear reactor channel B, comprises three sealed casings 4, 8, 13a interconnected by ball- and - socket joints 6, 7 and 11, 13 so that a push or pull action exerted on a member 14 of the upper casing may be transmitted to jaws 1 on the lower casing. The casing 4 encloses an electromagnet 2 for operating the jaws, feelers 21 for engagement by the fuel element A to cause automatic gripping action of the jaws and lamps 5 for illuminating the fuel element. The jaw action is described in detail with reference to Fig. 2 (not shown). An endoscope 3 extends through the casing 4 to present an image of the fuel element to ...

Refuelling of nuclear reactors

During unrodded refueling, the drive rods and the control rods and coolant-displacement rods, attached to the drive rods, are removed from a fuel assembly, preliminary to the transfer of the fuel assembly, and are reinserted in the reactor after a replacement fuel assembly has been positioned in the reactor. Prior to the transfer of a fuel assembly, a lifting rig is secured to the upper-internals support. A lift plate is removeably mounted on latches in a lower position of the lifting rig. The latches are released and the lift plate is connected to the drive rods. The lift plate is then raised and removeably mounted on latches in an upper position on the lifting rig. In this position, the control rods and coolant-displacement rods are in the guides in the upper internals of the reactor. During the lift-plate raising operation, the loading on the drive rods is monitored and if the loading exceeds a predetermined magnitude, the excess loading is indicated. After the lift plate and the rods ...

Improvements in or relating to manipulating tools

... 1,001,652. Fuelling reactors. COMMISSARIAT A L'ENERGIE ATOMIQUE. Sept. 18, 1962 [Sept. 18, 1961], No. 35478/62. Heading G6C. [Also in Division B8] A gripping device with jaws 43, Fig. 5, is supported on a pinion 23, Fig. 1, which is suspended by a chain 22, from a differential winch, which, by lowering the gripping device on to an object (e.g. a fuel element) to be lifted, causes the jaws to close, and by rotating the pinion moves sash bolts 25 to lock the jaws either open or closed. When the jaws are lowered on to a fuel element, a cam member 42, Fig. 5, attached to rods 50, 40, is pushed upwards against a spring 41 by a handle 48 on the element to close the jaws 43, Fig. 6. Upward movement of the rods 50, 40 also raises a member 45 so that a slot 47 therein is lifted clear of the end 25a of the sash bolt 25. Whilst the rods 50, 40 are raised the pinion 23 is rotated through 180 degrees by turning a wheel 17, Fig. 1, to allow a bolt 18 to be moved from a hole 20 to a hole 21. The movement ...

Improvements in and relating to safety release mechanisms

... 872,092. Controlling reactors. NUCLEAR POWER PLANT CO. Ltd. Aug. 14, 1959 [Sept. 8, 1958], No. 28768/58. Class 39(4). A safety release mechanism for releasing a member from a parent member in response to changes in pressure in a fluid in which the releasable member is immersed comprises a push rod attached to the releasable member and operable to trip a latch mechanism joining the releasable member to the parent member and a pressure sensitive device located in the releasable member and forming an enclosed space therein; the pressure sensitive device being responsive to pressure changes between the enclosed space and fluid surrounding the releasable member and exerting a force on the push rod sufficient to trip the latch mechanism when a predetermined pressure change occurs. Fig. 1 shows an arrangement for releasing a control or safety rod in a gascooled nuclear reactor. The control rod comprises a tube 2 containing boron and arranged between inner and outer stainless steel tubes 1, 3.

INTERNALS LIFTING DEVICE

Improvements relating to fuel charging and discharging apparatus for a nuclear reactor

... 877,423. Nuclear reactors; handling nuclear fuel elements. BOYD Ltd., WINNETT. Sept. 1, 1959 [Sept. 2, 1958], No. 28180/58. Class 39(4). A gas-cooled reactor having horizontal fuel element channels 2 in its graphite core 1 has a spherical pressure vessel 3 surrounded by cooling and shielding water 6 within concrete shielding 5, the channels 2 being charged and discharged by apparatus contained in auxiliary pressure vessels which are permanently connected to the vessel 3 and subjected to the pressure therein whereby the fuel elements may be loaded and unloaded whilst the reactor is under load and without the necessity of making any gas-tight connections. The auxiliary pressure vessels comprise elevator shafts 15 which extend upwardly from a central position disposed at each end of the reactor and each of which contains tracks 14 for an elevator dolly 19 supported by chains 19a, the top end of each shaft having an enlarged head 18. A series of horizontal tracks 12 is disposed adjacent each ...

Lifting devices

... 1,056,413. Article engaging devices for lifting and lowering. ENGLISH ELECTRIC CO. Ltd. Feb. 25, 1965 [Feb. 27, 1964], No. 8297/64. Heading B8H. A grab for moving fuel elements into or out of nuclear reactors comprises a hollow body 10, Fig. 1, attached to a rope 37 and having pivoted thereon jaws 12 and a probe 18 movable longitudinally in the body between an extended position and a retracted position for endwise engagement with the element, the probe having cam portions 20B, 20C, 20D for engaging projections 15, 16 on the jaws 12 to move the latter between its open and closed positions. The body is in three parts 10A, 10B, 10C and the part 10C is formed with four radial slots 11, each of which has disposed therein a jaw 12 provided with a gripping lug 14 and a radial locating fin 17. The probe 18 comprises a solid core 19 around which is rigidly secured a sleeve 20 having a nose 20A and the cam portions 20B, 20C, 20D, the portion 20D having lateral surfaces 20E and a lower surface 20F ...

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

DISTRIBUTION OF BURDENS DEVICE, IN PARTICULAR FOR A LIFTING WITNESS

MANIPULATOR FOR A NUCLEAR REACTOR

SYSTEMS AND METHODS FOR UNDERWATER TOOL POSITIONING

Systems and methods position tools about a flooded nuclear reactor during maintenance outages without overhead support or alignment structures being necessary, systems may include annular clamps for support from a reactor steam dam, a telescoping mast, a motor or other drive to extend or retract the mast, and/or an articulator to hold the payload and move the same about any degree of freedom. The telescoping mast may include several nested sections joined to a drive motor. Several different articulators are useable, including those with separate gearings for rotation about perpendicular axes and self-leveling wrists to orient tools in confirmed positions. Systems can be locally or remotely powered and controlled through powered and communicative connections to move about any position in a reactor annulus or core.

DEVICE FOR GRASPING A PENCIL CLUSTER IN A NUCLEAR FUEL ASSEMBLY

Lors du démantèlement d'un assemblage combustible de réacteur nucléaire, on réalise la préhension simultanée de tous les crayons, disposes selon un réseau à pas carre dans cet assemblage, au moyen d'un dispositif effectuant un serrage en bout des rangées de crayons. A cet effet, le dispositif comporte des couloirs dans lesquels on fait pénétrer les extrémités des deux rangées adjacentes de crayons. Dans ces couloirs sont emprisonnes des organes mobiles disposes de telle sorte que chaque crayon soit placé entre deux organes voisins. En appliquant dans chaque couloir un effort de serrage sur les organes mobiles d'extrémité on pince chaque crayon entre deux organes. De préférence, les organes mobiles sont munis de butées limitant l'effort de serrage appliqué individuellement sur chaque crayon. Pour combler les vides du réseau de crayons correspondant aux emplacements occupés par les tubes guides dans les assemblages, on place des rouleaux aux emplacements correpondants, dans les couloirs.

UPPER VESSEL TRANSPORT

A system for refueling a nuclear reactor is provided. The system includes a lower reactor vessel with a plurality of fuel rods and a plurality of control rods disposed therein, the lower reactor vessel further comprising an upper flange. An upper reactor vessel is provided which encloses a steam generator and a pressurizer, the upper reactor vessel further comprising a lower flange that matingly engages the upper flange of the lower reactor vessel. A transporter surrounds an outer surface of the upper reactor vessel, wherein the transporter is configured to translate the upper reactor vessel vertically toward and away from the lower reactor vessel and also to translate the upper reactor vessel horizontally toward or away from alignment with the lower reactor vessel.

SYSTEM FOR ASSEMBLING OR DISASSEMBLING A SEGMENTED ROD

An embodiment of the present invention takes the form of a system that allows for simultaneously assembling or disassembling multiple segmented nuclear fuel rods (hereinafter "segmented rods"). An embodiment of the present invention, may receive, secure, and move the segmented rods into a position that allows for performing the tasks of either assembly or disassembly, allowing for an operator to use a tool to complete the aforementioned tasks.

Pince de manutention

Mécanisme d'accouplement d'une barre à un arbre allongé

Vorrichtung zum Herausziehen eines Reaktorteiles aus einem Kernreaktor

Lade- und Bedienungseinrichtung in einer Kernreaktoranlage

Grappin

Mécanisme de levée

Kernreaktor

Atomkernreaktor

Dispositif de retenue en position d'au moins une pièce de matière fissile

Dispositif de réglage individuel du débit de fluide réfrigérant dans des canaux d'un réacteur nucléaire

Bras de manipulation pour réacteur nucléaire

Machine servant au chargement et au déchargement des canaux rectilignes d'une pile atomique

Vorrichtung zum Heben von Gegenständen

Pince de manutention

Einrichtung zum Transportieren von festen, spaltbares Material enthaltenden Blöcken

Installation de manutention d'éléments combustibles

Dispositif de chargement d'un réacteur nucléaire en assemblages d'éléments de combustible

Pince pour la préhension d'objets à surface parfaitement lisse

Installation de rechargement en combustible, pour un réacteur nucléaire

Kernreaktor

Vorrichtung zum Ein- und Ausbauen von Filterkerzen

MONTE-CHARGE POUR UN PUITS DE REACTEUR NUCLEAIRE.

Appareil de manutention

Vorrichtung zum Einführen und Entfernen von Gegenständen in einen bzw. aus einem dicht abgeschlossenen, zu einem Kernreaktor gehörenden Raum

Kernelementwechseleinrichtung

Appareil de manutention des éléments de combustible d'un réacteur nucléaire

Ladegerät für Brennelemente und Regelstäbe in einem Kernreaktor

Appareil de manipulation à distance

Appareil de soulèvement de plaques

Baustein für einen Reaktorkern

Grappin à billes

Gasgekühlter nuklearer Kernreaktor

Installation de chargement et de déchargement en combustible pour réacteur nucléaire

Dispositif comprenant un outil commandé pour effectuer la mise en place et le serrage ou le desserrage simultanés de deux boulons

Installation de rechargement en combustible pour réacteur nucléaire

Dispositif de manutention et d'orientation d'un élément prismatique à introduire dans le coeur d'un réacteur nucléaire

PROCEDURE FOR THE LOADING AND/OR UNLOADING A NUCLEAR REACTOR AND A SUPPORTING PIECE FOR THE EXECUTION OF THIS PROCEDURE.

Nuclear reactor and method for the disposal of one or more radioactive components from nuclear reactors of nuclear power stations.

Die Erfindung betrifft einen Kernreaktor mit einer Vorrichtung zum Entsorgen von einer oder mehreren radioaktiven Komponenten aus dem Kernreaktor umfassend eine erste Aufnahme, die zum Aufnehmen der einen oder mehrerer radioaktiver Komponenten ausgelegt ist, einen Rahmen, der zum Stützen der ersten Aufnahme im Kernreaktor ausgelegt ist, und eine Trennvorrichtung, die zum Trennen der einen oder mehrerer radioaktiver Komponenten in zwei oder mehr Teile während des Absenkens der einen oder mehrerer radioaktiver Komponenten in die erste Aufnahme ausgelegt ist. Die Erfindung umfasst ebenfalls ein Verfahren zum Entsorgen von einer oder mehreren radioaktiven Komponenten aus einem Kernreaktor umfassend das Montieren einer Vorrichtung zum Entsorgen der einen oder mehrerer radioaktiver Komponenten und das Bewegen der montierten Vorrichtung in einen Bereich eines Reaktorkerns (102). Ein weiteres Verfahren zum Entsorgen von einer oder mehreren radioaktiven Komponenten aus einem Kernreaktor umfasst ...

METHOD OF EXTRACTING PLUG AND REMOVABLE UNIT WHEN REFUELING NUCLEAR REACTOR

METHOD OF EXTRACTING PLUG AND UNIT PORTABLE OVERLOAD AT NUCLEAR REACTOR

Assembly for fuel element of nuclear reactor

PROCEDE DE CHARGEMENT-DECHARGEMENT D'UN REACTEUR NUCLEAIRE A NEUTRONS RAPIDES ET MACHINE DE CHARGEMENT-DECHARGEMENT POUR LA MISE EN OEUVRE DUDIT PROCEDE

L'invention concerne les techniques nucléaires. Le procédé faisant l'objet de l'invention est du type dans lequel le déchargement de l'assemblage combustible à remplacer 47 s'effectue par extraction de ce dernier de la zone active (coeur) du réacteur 2 par une machine de chargement-déchargement 1 le déplaçant en montée et le plaçant ensuite dans le corps étanche de ladite machine, ledit assemblage combustible étant, pendant ledit déchargement, refroidi par deux courants de gaz inerte dont l'un est amené sur la surface extérieure dudit assemblage tandis que l'autre est soufflé à travers l'assemblage, et est caractérisé en ce que le courant de gaz inerte destiné à traverser l'assemblage combustible à remplacer 47 est amené à contresens dudit mouvement de montée de ce dernier lors de son extraction de la zone active du réacteur. L'invention s'applique notamment aux réacteurs nucléaires refroidis par un métal liquide tel que par exemple le sodium.

PROCEEDED OF LOADING AND UNLOADING Of a NUCLEAR REACTOR HAS FAST NEUTRONS AND MACHINE OF PROCEEDED LOADING AND UNLOADING FOR the IMPLEMENTATION OF THE AFORESAID

CHARGE/DISCHARGE ARRANGEMENTS FOR NUCLEAR REACTORS

Equipment of fuel handling for nuclear reactor

Sliding assembly of fuel elements for nuclear reactors and its device of operation

Hook for the handling of the fuel rods of nuclear reactors

IMPROVEMENTS IN AND RELATING TO APPARATUS FOR ORIENTATING PRISMATIC ELEMENTS

Device of vertical handling and fixing of fuel assembly for nuclear reactor

Hoisting device, in particular for bars of atomic piles

Hoisting and handling equipment for nuclear reactor

Device of guidance and locking of a handling gripper of fuel elements in a nuclear reactor

Hook of handling

CHARGE/DISCHARGE ARRANGEMENTS FOR NUCLEAR REACTORS

FAST BREEDER REACTOR CORE AND METHOD OF PRETREATING NUCLEAR FUEL REPROCESSING

Separately exchangeable fuel inserts for - pressurized water reactos

DEVICE OF Dry HANDLING Of NUCLEAR FUEL ASSEMBLIES

L'invention concerne un dispositif de manutention à sec d'assemblages de combustible nucléaire comprenant une hotte de transfert (20) apte à être reliée à des moyens de levage et comportant un organe de préhension de l'assemblage de combustible à transférer porté par un mécanisme de levage intégré à la hotte et une table d'indexage (50) apte à être placée sur un château de transport (1) et comportant des moyens (55, 56, 57) de positionnement de la hotte (20) sur une alvéole du château de transport.

DEVICE FOR THE DRY HANDLING OF NUCLEAR FUEL ASSEMBLIES

A device for the dry handling of nuclear fuel assemblies is provided. The device includes a transfer basket which can be connected to a lifter and which includes a gripper for gripping the fuel assembly to be transferred, the gripper being supported by a lift built into the basket; and an indexing table which can be placed on a cask and which comprises a positioner for positioning the basket over a slot in the cask. 115-. (canceled)16. A device for the dry handling of nuclear fuel assemblies comprising:a transfer basket connectable to a lifter and having an inner gripper for gripping a fuel assembly to be transferred, the inner gripper supported by a lift built into the basket, the transfer basket including a bottom provided with valves pivoting between an open position for the passage of the fuel assembly to be transferred and a closed position of the basket; andan indexing table placeable on a cask and including a positioner for positioning the basket on a slot of the cask and orienting the inner gripper relative to the fuel assembly.17. The device as recited in wherein the basket comprises an upper portion including a double attachment system with a hook for the lifter claim 16 , a body containing the built-in lift bearing the inner gripper and a lower portion formed by the bottom provided with the valves.18. The device as recited in wherein the bottom of the basket includes a central opening for the passage of the inner gripper and the fuel assembly in the open position of the valves.19. The device as recited in wherein the valves have mutually complementary shapes to cover the central opening in the closed position of the valves.20. The device as recited in wherein each valve is formed by a triangular plate whereof the base is hingedly mounted on the bottom.21. The device as recited in wherein each valve is placed above the bottom and is associated with at least one movement element between the open and closed positions.22. The device as recited in wherein the ...

DEVICE FOR TURNING A CONTAINER, PARTICULARLY FOR NUCLEAR FUEL ASSEMBLY, TURNING ASSEMBLY, AND NUCLEAR POWER PLANT

A device for turning a container about a turning axis is provided. The device includes a stationary holding member and two bearing members which are spaced apart along the turning axis on each side of a space for receiving a container, and which are capable of being used for bearing on the container while enabling the rotation of the container about the turning axis relative to the bearing members. The device includes a movable holding member that is mounted onto the stationary holding member so as to rotate about the turning axis, at least one bearing member being supported by the movable holding member while being mounted onto the movable holding member so as to rotate about the drive axis, the or each bearing member supported by the movable holding member not rotating about the turning axis relative to the stationary holding member when the movable holding member rotates about the turning axis relative to the stationary holding member. 117-. (canceled)18. A device for turning a container about a turning axis comprising:a stationary holding member;two bearing members which are spaced apart along the turning axis on each side of a space for receiving the container and which are capable of being used for bearing on the container while enabling the rotation of the container about the turning axis relative to the bearing members;a movable holding member that is mounted on to the stationary holding member so as to be rotatable around the turning axis, at least one of the bearing members being supported by the movable holding member while being mounted onto the movable holding member, so as to rotate about the turning axis, the or each bearing member supported by the movable holding member not rotating about the turning axis relative to the stationary holding member when the movable holding member rotates about the turning axis relative to the stationary holding member.19. The turning device according to further comprising a clamp capable of holding the or each bearing ...

Fuel exchange apparatus

A fuel exchange apparatus, comprising: a traveling carriage moving horizontally in one direction; a traversing carriage moving horizontally on the traveling carriage in a direction orthogonal to the one direction in which the traveling carriage moves; and a fuel holding unit attached to the traversing carriage, and including an telescopic tube enabling to extend and contract, a holding tool for holding a fuel assembly and releasing the held fuel assembly, and a lifter for raising and lowering the holding tool by winding and running out linear members for suspending and supporting the holding tool from the traversing carriage, wherein the holding tool is selectively placed in a constrained state in which the holding tool is subject to a constraint by the telescopic tube and in a freely suspended state in which the holding tool is released from the constraint by the telescopic tube and freely suspended by the linear members.

SYSTEMS AND METHODS OF REMOTE CONTROL ROD DRIVE DECOUPLING

Systems join with a control rod drive and expand or contract to displace elements necessary for decoupling. Joining structures affix to on sides of the control rod drive allow discriminatory jacking by a powered drive also in contact with the control rod drive. A moveable piston tube can be displaced by this jacking with hundreds or thousands of pounds of force with respect to the control rod drive. Probes and other instrumentation and sensors are useable in the systems to accurately measure any of piston tube displacement, temperature, malfunction; drive power status, displacement or speed; and communications status. Manual interaction with the systems are not required during the jacking, and installation and removal of the systems requires no tools or great amount of time or effort. Through remote operation and brief installation, human exposure to radiation about control rod drives is minimized. 1. A remote decoupling system for use in a nuclear reactor , the system comprising:an attachment structure configured to removably secure to a control rod drive of the reactor such that the control rod drive and attachment structure do not move relative to one another in a vertical direction; anda jack secured to the attachment structure, wherein the jack is configured to displace a piston tube of the control rod drive in the vertical direction relative to the control rod drive and the attachment structure without human contact.2. The system of claim 1 , wherein the jack includes a port configured to provide mechanical securing claim 1 , electrical communications claim 1 , and electrical power.3. The system of claim 1 , wherein the attachment structure includes claim 1 ,a sleeve shaped to fit around a lower flange of the control rod drive, anda clamp arm connecting to the sleeve and configured to attach to a backside of the flange.4. The system of claim 3 , wherein the clamp arm is rotatable with respect to the sleeve and extendable claim 3 , and wherein the clamp arm ...

SYSTEM FOR TRANSFER OF FUEL ELEMENTS IN A NUCLEAR POWER PLANT

Fuel elements are moved between upper and lower pools of a nuclear plant through a conveyor tube having upper and lower ends in the upper and lower pools. A transport basket movable internally along the tube and into which at least one of the fuel elements can be placed can travel through the conveyor tube. A blocking element at one end of the tube can fully close the conveyor tube. A traction cable guided through the conveyor tube raises and lowers the transport basket through the tube. An intermediate partially closing blocking element offset from the fully closing blocking element in the tube is movable between an open position allowing the basket to pass and a closed position blocking such passage and is formed with a cable passage through which the traction cable can pass in the closed position. 1. In combination with a nuclear power plant having an upper pool and a lower pool with a liquid level of the upper pool above a liquid level of the lower pool , a transfer system for moving fuel elements between the upper pool and the lower pool , the transfer system comprising:a conveyor tube having an upper end at the upper pool and a lower end at the lower pool and extending between the upper and lower ends at an acute angle to the vertical;a transport basket movable internally along the tube and into which at least one of the fuel elements can be placed for transfer through the conveyor tube;a fully closing upper blocking element at the upper end of the tube that can fully close the conveyor tube at the upper end;a cable hoist having a traction cable guided through the conveyor tube for raising and lowering the transport basket through the conveyor tube;a lower fully closing lower blocking element without a cable passage at the lower end; andan intermediate partially closing blocking element between the upper and lower fully closing blocking elements in the tube, movable between an open position allowing the basket to pass and a closed position blocking such ...

Integrated System for Forming and Transporting Packaging Assemblies, and the Assembly, Filling and Disassembly Stations Thereof

The invention relates to an assembly consisting of a plurality of packaging bottles () for conditioning, storing and transporting radioactive bars or tubes, hereinafter called fagot assembly (), wherein: said bottles () are identical and interchangeable; and said bottles are attached to each other in order to form a fagot or a bundle (), by means of quick-fastening means (), said fagot () comprising N bottles, N≧2; characterised in that said bottles () are formed from steel and are thicker at one of the two ends thereof, over a certain length. 223. The fagot assembly () according to claim 1 , characterized in that it is modular and has a variable geometry claim 1 , i.e. claim 1 , it can be subdivided or dimensioned in smaller subassemblies claim 1 , still using the same fastening means ().3212. The fagot assembly () according to claim 1 , characterized in that each of said bottles () is a type of packaging corresponding to the Type A certification of the IAEA Regulation for the transport of radioactive materials claim 1 , and the fagot assembly () also corresponds to said Type A certification.424. A use of a fagot assembly () according to claim 1 , for conditioning claim 1 , storing and transporting reformed guide tubes for control cluster rods () coming from pressurized or boiling water nuclear reactors.5611222. A handling installation () for filling Type A packaging bottles () with radioactive bars or tubes in the building of a nuclear reactor claim 1 , said bottles () forming a fagot assembly () according to claim 1 , said installation being integrated into the fagot assembly () so that the ground footprint of that integrated installation is limited to the dimensions of the fagot assembly ().6628910. The handling installation () according to claim 5 , characterized in that the fagot assembly () is topped by walkways () and equipped with ladders () and lifting means ().75312. An installation for the assembly and disassembly () with quick-fastening means () of Type ...

METHOD OF EXTRACTING PLUG AND REMOVABLE UNIT WHEN REFUELING NUCLEAR REACTOR

A method of the plug and removable block extraction when reloading the nuclear reactor. The invention relates to nuclear engineering, in particular to a process of the plug and the removable block extraction from a fast reactor with a heavy liquid metal coolant. The technical result consists in extracting the plug and the removable block without fuel assemblies from the nuclear reactor using a complex of handling equipment under radiation safety conditions. The method of the plug removable block extraction involves preliminary installation of handling equipment, removing the plug from the reactor monoblock, as well as transportation and positioning of the plug in the plug shaft, unloading the removable block, its transportation and placing the removable block in the shaft for the removable block disassembly. 1. A method of plug and removable block extraction during nuclear reactor reloading which consists in the following: the plug transportation device is installed on the reactor plug , an additional cargo is installed on the plug transportation device , cable reduction box internal frame part is installed and fixed on the reactor monoblock cover , the plug transportation device middle part is turned into a position where its projections enter into the operational area of the cable reduction box fixing element , the additional cargo is dismantled and the external part of cable reduction box is installed on the reactor monoblock , the internal media of the cable reduction box cavity is replaced , the guide channel is installed on the cable reduction box , the reloading armor is installed on the guide channel , the internal media of the reloading armor and guide channel is replaced , the plug transportation device with the plug is moved into the reloading armor , the reloading armor with the plug is transported into the plug shaft where the plug is unloaded , the guide channel is re-installed on the cable reduction box , the reloading armor with the removable block ...

NUCLEAR REACTOR SYSTEM WITH LIFT-OUT CORE ASSEMBLY

A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums. 1. A nuclear power reactor system comprising: a vessel inlet and a vessel outlet disposed coaxially with the vessel inlet;', 'a core receptacle defining a central axis and comprising a set of locating datums to receive a nuclear reactor core;', 'a set of control drums disposed about a periphery of the core receptacle; and', 'a set of control drum actuators coupled to the set of control drums and configured to selectively position each of the set of control drums;, 'a reactor vessel comprising a moderating core structure comprising a set of graphite prismatic blocks arranged adjacent a set of vertical flow channels configured to pass a working fluid adjacent the set of graphite prismatic blocks to the vessel outlet;', 'a set of locating features configured to mate with the locating datums in the reactor vessel to locate the moderating core structure in the core receptacle and along a flow path between the vessel inlet and the vessel outlet; and', 'a lift-out support plate configured to vertically support the moderating core structure during insertion of the moderating core structure into the core receptacle at a ...

NUCLEAR REACTOR SYSTEM WITH LIFT-OUT CORE ASSEMBLY

A modular nuclear reactor system includes a lift-out, replaceable nuclear reactor core configured for replacement as a singular unit during a single lift-out event, such as rather than lifting and replacing individual fuel assemblies and/or fuel elements. The system includes a reactor vessel and a power generation system configured to convert thermal energy in a high temperature working fluid received from the reactor vessel into electrical energy. The reactor vessel includes: a vessel inlet and an adjacent vessel outlet arranged near a bottom on the vessel; a vessel receptacle configured to receive a unified core assembly; locating datums in the base of the vessel receptacle and configured to constrain a core assembly in multiple degrees of freedom; and an interstitial zone surrounding the vessel receptacle and housing a set of control or moderating drums. 1. An automated method for installing a nuclear reactor core comprising:locating a shielded core transporter enshrouding a nuclear reactor core to a lowering position over a vessel;aligning a set of locating features arranged on the nuclear reactor core to a set of datum arranged within the vessel adjacent a working fluid plenum;lowering the nuclear reactor core from the shielded core transporter into the vessel such that the set of locating features engage with the set of datum;disengaging a lift adapter from a lift-out support plate arranged with the nuclear reactor core and into the shielded core transporter;removing the shielded core transporter from the lowering position;arranging a vessel head onto the vessel; andsealing the vessel head onto the vessel.2. The method of claim 1 , further comprising prior to locating the shielded core transporter enshrouding the nuclear reactor core to the lowering position over the vessel:verifying that a human is in a safe location distal from the shielded core transporter and the vessel by registering a unique identifier of the human in the safe location distal from the ...

MODULAR LOWER MOVING SYSTEM FOR NUCLEAR FUEL HANDLING AND METHOD OF REFUELING NUCLEAR FUEL USING THE SAME

The modular lower moving system for nuclear fuel handling includes: a lower reactor vessel assembly including nuclear fuel loaded therein; a carrier having a space allowing the lower reactor vessel assembly to be accommodated therein; a rail extending from a reactor area to a fuel handling area; a transfer cart horizontally movable along the rail; a lifting device installed at the transfer cart, movable upward or downward with respect to the transfer cart; and a drive device configured to supply power to the transfer cart and the lifting device. The method of refueling nuclear fuel using the modular lower moving system includes a carrier lifting process, a lower reactor vessel assembly detachment process, a process of accommodating the lower reactor vessel assembly in the carrier, a carrier lowering process, a transfer cart movement process, a nuclear fuel offloading process, and a nuclear fuel loading process. 1. A modular lower moving system for nuclear fuel handling , the modular lower moving system comprising:a lower reactor vessel assembly installed below a reactor vessel located in the reactor area, detachable from the reactor vessel, and comprising nuclear fuel loaded therein;a carrier having a space allowing the lower reactor vessel assembly detached from the reactor vessel to be accommodated therein;a rail installed at a bottom of the transfer canal and extended from the reactor area to the fuel handling area;a transfer cart horizontally movable along the rail;a lifting device installed on the transfer cart, horizontally movable along the rail along with the transfer cart, and movable upward or downward with respect to the transfer cart; anda drive device configured to supply power to the transfer cart and the lifting device,wherein the carrier is assembled on the lifting device to be lifted or lowered via the lifting device, the lower reactor vessel assembly detached from the reactor vessel is accommodated in the carrier, and the carrier is horizontally ...

Inclined Hoist of Nuclear Reactor

The inclined hoist of a nuclear reactor comprising a trolley with a sleeve for SFA, which moves along a rail track in an inclined corridor by means of a cable . At the entry into the inclined corridor , a guide block is installed, equipped with an asymmetric channel for routing the cable and installed at an angle β relative to the track, satisfying the condition: 1. The inclined hoist of a nuclear reactor , comprising a trolley with a sleeve for installation of spent fuel assemblies moving along a rail track in an inclined corridor , a drum with a cable , a drive , characterized in that a guide block is installed at the entrance to the inclined corridor , wherein this block has a channel for passage of the cable and is installed under angle β relative to the track , satisfying the condition:{'br': None, 'i': 'tgβ=t/πD'}where β is an angle of inclination of the guide block to the track;t is a pitch of cable grooves on the drum;D is a diameter of the drum.2. The inclined hoist according to claim 1 , characterized in that the guide block channel is asymmetric claim 1 , and its axis is located along the cable movement trajectory. This application is a US 371 Application from PCT/RU2017/000179 filed Mar. 29, 2017, which claims priority to Russia Application 2016112291 filed Apr. 1, 2016, the technical disclosures of which are hereby incorporated herein by reference.The invention relates to the field of nuclear engineering and can be used as part of handling equipment of nuclear reactor.A fast neutron nuclear reactor with a sodium coolant is known, that uses an inclined hoist (conveyor) to handle spent fuel assemblies (SFA), wherein the upper part of the hoist is located in the gas atmosphere of an discharge pit, and the lower part—in the water of a suppression pool (Moscow, Mashinostroyeniye, 2005, “Machine building in nuclear industry”, Book 1, Volume IV-25, p. 345).Arrangement of the inclined hoist and the suppression pool with cooling water in the same building as the ...

Rail Track for Inclined Hoist of Nuclear Reactor

The invention relates to the field of nuclear engineering and can be used as part of handling equipment of nuclear reactor. 1. A rail track for the inclined hoist of the nuclear reactor providing the movement of the trolley with the sleeve for installation of the spent fuel assemblies along the inclined corridor between the egression pit and the suppression pool , which is made with an alternation of the rectilinear and curvilinear sections , wherein the initial rectilinear section and the final rectilinear section have the same inclination angle α.2. According to claim 1 , the rail way is characterized in that the inclination angle α of any rectilinear sections is chosen according to the condition tg α>k claim 1 ,where α is the inclination angle of the rectilinear sections;k is the friction coefficient of the trolley and the track. This application is a US 371 Application from PCT/RU2017/000180 filed Mar. 29, 2017, which claims priority to Russia Application 2016112292 filed Apr. 1, 2016, the technical disclosures of which are hereby incorporated herein by reference.The invention relates to the field of nuclear engineering and can be used as part of handling equipment of nuclear reactor.A fast neutron nuclear reactor with a sodium coolant is known, that uses an inclined hoist (conveyor) to handle spent fuel assemblies (SFA), wherein the upper part of the hoist is located in the gas atmosphere of an egression pit, and the lower part—in the water of a suppression pool (Moscow, Mashinostroyeniye, 2005, “Machine building in nuclear industry”, Book 1, Volume IV-25, p. 345).Arrangement of the inclined hoist and the suppression pool with cooling water in the same building as the reactor reduces the reactor unit reliability and safety, since in case if the suppression pool wall loses tightness in an emergency situation (for example, during an earthquake), water can enter a room with radioactive sodium equipment of the first circuit, which can lead, with the active ...

Systems and Methods for Transferring Spent Nuclear Fuel From Wet Storage to Dry Storage

Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.

SPENT FUEL TRANSFER DEVICE FOR TRANSFERRING SPENT FUEL BETWEEN STORAGE POOLS

Provided is a device for transferring spent fuel between spent fuel storage pools. The device includes a transfer container extending in a direction, disposed in a vertical direction, and containing spent fuel therein; a guide frame configured to guide the transfer container while maintaining a vertical orientation of the transfer container; and a transfer unit configured to transfer the transfer container along the guide frame. 1. A device for transferring spent fuel between spent fuel storage pools , the device comprising:a transfer container extending in a direction, disposed in a vertical direction, and containing spent fuel therein;a guide frame configured to guide the transfer container while maintaining a vertical orientation of the transfer container; anda transfer unit configured to transfer the transfer container along the guide frame.2. The device of claim 1 , wherein the transfer container comprises a plurality of first holes for cooling down the spent fuel.3. The device of claim 1 , wherein the transfer container comprises a second hole on a lower portion thereof for cooling-down and discharging cooling water.4. The device of claim 1 , wherein a bumper surrounds with an upper end portion of the transfer container in a direction perpendicular to a lengthwise direction of the transfer container so as to maintain a distance between the transfer container and a spent fuel handling machine that transfers the spent fuel to the transfer container.5. The device of claim 1 , wherein the guide frame comprises support frames disposed on a bottom surface of a refueling cavity in a vertical direction to be spaced apart from each other claim 1 , and a guide rail disposed in a horizontal direction to be coupled to the support frames.6. The device of claim 5 , further comprising a guide wheel coupled to the transfer container claim 5 ,wherein the guide wheel moves along the guide rail.7. The device of claim 1 , wherein the transfer unit comprises:a pulley coupled to ...

NUCLEAR REACTOR REFUELING METHODS AND APPARATUSES

Refueling of a nuclear reactor () includes removing a fuel assembly (). The removal method includes lowering a lifting tool () of a crane () onto a top of the fuel assembly. The lowered lifting tool including a plurality of downwardly extending elements () that surround and vertically overlap a portion () of a control rod assembly () extending above the top of the fuel assembly. The downwardly extending elements are locked with corresponding mating features () at the top of the fuel assembly to connect the lifting tool with the fuel assembly. The connected fuel assembly is moved into a spent fuel pool () using the crane, and the lifting tool is disconnected from the top of the fuel assembly by unlocking the downwardly extending elements from the corresponding mating features at the top of the fuel assembly. 1. A method of refueling a fuel assembly from a reactor core of a nuclear reactor , the method comprising:connecting a lifting tool of a crane with a plurality of lifting pins of the fuel assembly, each lifting pin being non-rotatably affixed to an upper nozzle plate of the fuel assembly and extending upwardly therefrom, the lifting tool comprising a plurality of downwardly extending bars, wherein each of the downwardly extending bars has an upper portion and a lower portion capable of circumferential rotation independent of both the upper portions and the other downwardly extending bars, the connecting including forming a bayonet connection by lowering the downwardly extending bars over the lifting pins so that the lifting pins are disposed within the lower portions of the downwardly extending bars and circumferentially rotating only the lower portion of each of the downwardly extending bars to create a mating connection between each of the downwardly extending bars and the lifting pin over which each of the downwardly extending bars was lowered, whereinthe mating connection is made between a grooved portion and a narrowed portion of the lifting pin and a recess ...

Method and Apparatus for the Shielded Relocation of a Nuclear Component

A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement. 1. A method for relocating the nuclear plant component with the machine of comprising the steps of:moving the bridge assembly to position the machine over the nuclear plant component to be relocated with the gripper assembly aligned with the nuclear plant component;moving the moveable mast downward with the mast shield canister suspended below the gripper;supporting the lower end portion of the mast shield canister above the nuclear plant component with the nuclear plant component in line with the central opening through which the moveable mast can extend;lowering the moveable mast through the central opening;engaging the gripper assembly on a top surface of the nuclear plant component;raising the moveable mast to withdraw the moveable mast and the nuclear plant component upward within the central opening; andmoving the bridge assembly to position the nuclear plant component at a new location.2. The method of including the steps of:lowering the moveable mast at the new location;disengaging the gripper assembly from the nuclear plant component; andraising the moveable mast.3. The method of wherein the new location is a transfer cart comprising a moveable platform for transporting the nuclear plant component ...

METHOD AND APPARATUS FOR THE SHIELDED RELOCATION OF A NUCLEAR COMPONENT

A nuclear component transfer device that incorporates a shielded canister into the mast design of a conventional nuclear refueling machine. A moveable mast telescopes within a stationary mast which is attached to a bridge for lateral positioning. The canister allows for the addition of shielding that is positioned with the movement of the moveable mast without additional motorized components to deploy the shielding during nuclear component movement. The nuclear component is drawn up into the shielded canister as the moveable mast lifts the nuclear component. The nuclear component is then placed into a transfer cart that is also fitted with a shielded canister. The transfer is made without exposing the nuclear components resulting in completely shield movement. 1. A machine for moving a nuclear plant component from a first location to another comprising:a bridge assembly for positioning the machine over the nuclear plant component to be moved;a stationary mast supported from the bridge assembly at a first end and extending down from the bridge assembly in a direction of the nuclear plant component;a moveable mast, telescopingly nested within the stationary mast and configured to extend from the stationary mast and retract within the stationary mast under the control of an operator;a mast shield canister having an axially extending central opening through which the moveable mast can extend, the mast shield canister having an upper end portion and a lower end portion, with a first stop on the upper end portion of the mast shield canister and/or on a lower end of the moveable mast preventing the lower end of the moveable mast from withdrawing out of the upper end portion of the mast shield canister and a second stop on either or both the stationary mast or the mast shield canister that prevents the mast shield canister from moving more than a preselected distance from the stationary mast, the mast shield canister being sized at least to fit over substantially the full ...

APPARATUS AND METHOD FOR REMOVING THE UPPER INTERNALS FROM A NUCLEAR REACTOR PRESSURIZED VESSEL

A lifting fixture for removing the upper internals from a reactor to provide access to the core for refueling that does not require flooding of a refueling canal. The invention provides a means of shielding and ventilation that is integral to a lifting rig used to remove the upper internals. The lifting rig provides a means for personnel to decouple the drive rods from the rod cluster control assemblies so the drive rods can be lifted from the core with the upper internals while shielding maintenance personnel without flooding the area above the reactor. 1. An upper internals package lifting fixture for refueling a reactor having a reactor vessel with an upper flange surrounding an opening in the reactor vessel that is sealed by a mating flange on a closure head , the reactor vessel enclosing an upper internals package that seats above a plurality of fuel assemblies within a core of the reactor , the upper internals package including control rod assembly drive rod travel housings in which control rod assembly drive rods are housed and through which the drive rods travel along a vertical path , the upper internals package lifting fixture comprising:a shield plate sized to cover the opening in the reactor vessel when supported on the reactor vessel upper flange, the shield plate being formed from a material that lessens the radiation exposure of workers working above the shield plate covering the reactor vessel opening;a lifting rig formed integral with and extending above the shield plate; andmeans for attaching the shield plate to the upper internals package.2. The upper internals package lifting fixture of wherein the shield plate includes openings to access the control rod assembly drive rods.3. The upper internals package lifting fixture of wherein the openings to access the control rod assembly drive rods respectively include a tubular penetration through the shield plate that align and mate with the rod travel housings in the upper internals package.4. The ...

METHOD AND APPARATUS FOR REFUELING A NUCLEAR REACTOR HAVING AN INSTRUMENTATION PENETRATION FLANGE

Apparatus and a method for retracting in-core instrument thimble tubes from the reactor core prior to refueling a nuclear reactor with top mounted instrumentation. The apparatus includes a penetration flange interposed between the head flange and the reactor vessel flange through which the instrumentation cabling passes. The penetration flange is connected to the upper internals and can be raised relative thereto to retract instrumentation thimbles from the core prior to removal of the upper internals from the reactor vessel for refueling. The penetration flange is removed from the vessel with the upper internals. 1. A nuclear reactor comprising:an elongated reactor vessel enclosed at a lower end and having an open upper end on which an annular flange is formed and a central axis extending, along an elongated dimension;a reactor vessel head having an annular portion on an underside of the bead that is machined to form a sealing surface;a first removable annular seal ring, sized to seat on the reactor vessel flange between the flange and the sealing surface on the underside of the reactor vessel head, the seal ring being interposed between the sealing surface on the underside of the vessel head and the flange on the reactor vessel and having a thickness sized to sealably accommodate one or more radial passages through which one or more instrument conduits pass from outside of the reactor vessel to an interior thereof to communicate instrumentation signals out of a core of the nuclear reactor, the core comprising a plurality of fuel assemblies;an upper internals package supported above the core within the reactor vessel and having a plurality of hollow support columns respectively having a substantially vertical passage therethrough, that extends through and between an upper core plate and an upper support plate of the upper internals package, the passage through the upper core plate being aligned with a corresponding instrument thimble within one of the fuel ...

NUCLEAR FUEL ASSEMBLY HANDLING APPARATUS

A fuel assembly handling tool that can be lowered onto the top nozzle of a fuel assembly, positively latch the top nozzle, unlatch from the top nozzle, and be raised off the top nozzle of the fuel assembly. The tool head, that interfaces with the top nozzle has load bearing grippers that latch onto the fuel assembly, that are located in a storage position up within the tool while the tool is lowered onto the fuel assembly. The gripper fingers are then lowered into position during the latching process, and are raised back to the storage position during the unlatching process. In the storage position, the gripping fingers are spaced above the fuel assembly top nozzle when the tool head is resting on the nozzle. 1. A fuel assembly handling tool comprising:a bail configured to be connected to a crane or other hoist;a bail plate connected to the bail as to be freely supported by the bail;a tool body freely supported at an upper end from the bail plate and extending between the bail plate and a lower end with the length between the upper and lower ends being gauged to access a top nozzle of a fuel assembly; anda tool head connected to the lower end of the tool body and sized to house a gripper assembly in a withdrawn position so that the gripper assembly is out of contact with the top nozzle of the fuel assembly when the tool head contacts or otherwise rests on the top nozzle, the gripper assembly being operable to extend below its withdrawn position to an extended position to grip a portion of the top nozzle of the fuel assembly to support the fuel assembly as the crane or other hoist lifts the bail.2. The fuel assembly handling tool of including an actuator arm accessible from the bail plate and operable to extend or withdraw the gripper a assembly to the extended or withdrawn position.3. The fuel assembly handling tool of wherein the gripper assembly is moved to the withdrawn position or the extended position by respectively raising or lowering the actuator arm in a ...

BOILING WATER REACTOR BLADE GUIDE AND EXCHANGE TOOL

A combined blade guide and exchange tool, include a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod. 1. A method of removing a control rod and fuel support from a cell of a boiling water reactor , comprising:inserting into the cell a blade guide tool having a pair of collet housings at a lower end of the blade guide tool so that the pair of collet housings are received in respective fuel bundle pockets in the fuel support, the blade guide tool including a pair of fuel support grapple actuating rods each including a first end engaging a respective one of a pair of collets within the pair of collet housings and having a second end disposed at an upper end of the blade guide tool;assembling a blade exchange tool to the upper end of the blade guide tool, the blade exchange tool including a pair of upper collets for engaging the pair of fuel support grapple actuating rods, the blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool;actuating the pair of upper collets to engage the pair of lower collets via advancement of the fuel support grapple actuating rods and causing the pair of lower collets to engage the fuel bundle pockets in the fuel support; andengaging the hook assembly to a control rod and ...

CANISTER TRANSFER SYSTEM WITH INDEPENDENT TRAVELING SHIELDED BELL

A transfer system for spent fuel canisters includes a carrier, a shielded bell trolley movable along the carrier and carrying a shielded bell, and a canister trolley movable along the carrier and carrying a lifting mechanism for raising and lowering the spent fuel canister into and out of the shielded bell. The canister trolley can move along the carrier independent of the shielded bell trolley and the shielded bell trolley can move along the carrier independent of the canister trolley. The shielded bell trolley and the canister trolley can be selectively interlocked for selected transfer operations. 1. A method for moving a spent fuel canister comprising the steps of , in combination:moving a shielded bell trolley along a carrier while carrying a shielded bell to position the shielded bell over the spent fuel canister;moving a canister trolley along the carrier while carrying a lifting mechanism for raising and lowering the spent fuel canister into the shielded bell to position the lifting mechanism over the spent fuel canister;wherein the canister trolley is configured to move along the carrier relative to the shielded bell trolley;lifting the spent fuel canister with the lifting mechanism carried by the canister trolley into the shielded bell carried by the shielded bell trolley; andmoving the shielded bell trolley and the canister trolley together along the carrier at the same time while the lifting mechanism of the canister trolley supports the spent fuel canister within the shielded bell carried by the shielded bell trolley.2. The method of claim 1 , further comprising the step of moving the carrier along a pair of stationary spaced-apart rails.3. The method of claim 2 , wherein the carrier includes a first pair of spaced-apart rails for supporting the canister trolley and a second pair of spaced-apart rails for supporting the shielded bell trolley.4. The method of claim 3 , wherein the first pair of spaced-apart rails is parallel to the second pair of spaced- ...

APPARATUS AND METHOD FOR REMOVING THE UPPER INTERNALS FROM A NUCLEAR REACTOR PRESSURIZED VESSEL

A lifting fixture for removing the upper internals from a reactor to provide access to the core for refueling that does not require flooding of a refueling canal. The invention provides a means of shielding and ventilation that is integral to a lifting rig used to remove the upper internals. The lifting rig provides a means for personnel to decouple the drive rods from the rod cluster control assemblies so the drive rods can be lifted from the core with the upper internals while shielding maintenance personnel without flooding the area above the reactor. 1. A method of removing an upper internals package from a nuclear reactor having a reactor vessel with an upper flange surrounding an opening in the reactor vessel that is sealed by a mating flange on a closure head , the reactor vessel enclosing the upper internals package that seats above a plurality of fuel assemblies within a core of the reactor , the upper internals package including a plurality of rod travel housings in which control rod assembly drive rods are housed and through which the drive rods travel along a vertical path , the method comprising the steps of:removing the closure head from the reactor vessel;lowering a shield plate over the opening in the reactor vessel, the shield plate being sized to cover the opening when supported on the reactor vessel upper flange and being formed from a material that lessens the radiation exposure of workers working above the shield plate covering the reactor vessel opening, the shield plate including an integral lifting rig extending above an upper surface thereof;attaching the shield plate to the upper internals package; andraising the shield plate to withdraw the upper internals package out of the reactor.2. The method of wherein the shield plate includes openings to access the control rod assembly drive rods claim 1 , the access openings including a drive rod latching tool that is reciprocally moveable along a substantially vertical travel path through the ...

METHOD AND APPARATUS FOR INSPECTING A FUEL ASSEMBLY

A fuel assembly inspection system that utilizes a pressure transducer mounted to a utility's spent fuel handling tool to detect a relative change in depth of a fuel assembly during fuel inspections. The system then wirelessly transmits the signal to a fuel inspection recording system, which converts the signal to a relative height along the fuel assembly being viewed by a camera, and displays the relative height along with the applicable fuel assembly feature being viewed by the camera (e.g., nozzle, grid, span) via a text overlay on the video image of the inspection. 1. A method of remotely inspecting a nuclear fuel assembly stored in a cell within a rack in a lower portion of a spent fuel pool , the method comprising the steps of:supporting a camera within the spent fuel pool above the rack focused above the cell in which the nuclear fuel assembly is stored, the camera having an output which is transmitted to a processing apparatus outside of the spent fuel pool;fastening a pressure transducer to a long handled fuel assembly handling tool at a fixed distance above a connector on the fuel assembly handling tool that attaches to the fuel assembly and below a point on the fuel assembly handling tool that will remain submerged within the spent fuel pool when the fuel assembly handling tool raises the fuel assembly substantially completely out of the rack, the pressure transducer having an output representative of the depth within the spent fuel pool at the pressure transducer elevation, which pressure transducer output is transmitted to the processing apparatus;lowering the connector to the fuel assembly;attaching the connector to the fuel assembly;raising the fuel assembly out of the cell with the fuel assembly handling tool as the camera records a portion of the fuel assembly in view of the camera and transmits an image of the portion of the fuel assembly in view as at least part of the camera output to the processing apparatus;correlating, in the processing ...

LIFTING SHACKLE OF HEAD ASSEMBLY FOR NUCLEAR REACTOR

A lifting shackle of a head assembly for a nuclear reactor according to one embodiment of the present invention comprises: a first member and a second member which extend in parallel to each other in a predetermined thickness and length and respectively have an upper portion and a lower portion; a first connection member which connects the upper portion of the first member and the upper portion of the second member to each other and is coupled to a hook; coupling sections which are respectively provided at the lower portions of the first member and the second members and has a hollow portion so as to be coupled to the head assembly for a nuclear reactor via pins; and stress reducing sections which are formed at the upper portions of the first member and the second member such that the stress reducing sections extend from the first connection member to the first member and the side end of the second member at a predetermined curvature and protrudes upwards so as to reduce bending stress that is applied to the first connection member. 1. A lifting shackle for a head assembly for a nuclear reactor , which is connected to a hook to the head assembly , comprising:a first member and a second member that extend with a constant thickness and a constant length that extend in parallel to each other with a constant thickness and a constant length, each including an upper portion and a lower portion;a first connection member that couples an upper portion of the first member and an upper portion of the second member, and that is connected to the hook;connection units, each having a through hole in the center, into which a rod is inserted to couple the connection unit and the head assembly for the nuclear reactor, that are provided to lower portions of the first member and the second member, respectively; andstress reduction portions that are formed in the upper portions of the first member and the second member in such a manner as to extend at a constant curvature from the first ...

SYSTEM FOR HANDLING FUEL ELEMENTS

Fuel elements are moved between an upper pool and a lower pool of a nuclear plant by a conveyor tube having an upper end at the upper pool and a lower end at the lower pool and extending at an acute angle to the vertical between the ends. A plurality of transport baskets can move through the conveyor tube, each holding at least one of the fuel. An upper transfer device at the upper end in the upper pool loads the fuel elements into or unloads them from the transport baskets. A lower transfer device in the lower pool loads fuel elements into or unloads them from the transport baskets. Each transfer device can hold two of the transport baskets that are displaceable for positioning above or below the conveyor tube and movable during displacement through the tube between a vertical transfer position and an angled transport position. 1. A system for transferring fuel elements between an upper pool and a lower pool of a nuclear plant , the system comprising:a conveyor tube having an upper end at the upper pool and a lower end at the lower pool and extending at an acute angle to the vertical between the ends;a plurality of transport baskets movable through the conveyor tube and into each of which at least one of the fuel elements can be placed for transport through the conveyor tube;an upper transfer device at the upper end in the upper pool for loading the fuel elements into or unloading them from the transport baskets; anda lower transfer device in the lower pool for loading fuel elements into or unloading them from the transport baskets, each of the devices being adapted to hold two of the transport baskets, the baskets being displaceable for positioning above or below the conveyor tube and being movable during displacement through the tube between a vertical transfer position and an angled transport position.2. The system defined in claim 1 , wherein the upper and the lower transfer device each have two pivot frames into each of which a respective transport basket can ...

SYSTEM FOR HANDLING FUEL ELEMENTS

A system for transferring fuel elements between an upper pool and a lower pool of a nuclear plant has a conveyor tube having an upper end at the upper pool and a lower end at the lower pool. A transport basket movable internally along the tube and into which at least one of the fuel elements can be placed can travel through the conveyor tube. A blocking element at one end of the tube that can fully close the conveyor tube at the respective end. A cable hoist has a traction cable guided through the conveyor tube for raising and lowering the transport basket through the conveyor tube. An intermediate partially closing blocking element offset from the fully closing blocking element in the tube is formed with a cable passage through which the traction cable can pass in the closed position. 1. A transfer system for transfer of fuel elements between an upper pool and a lower pool of a nuclear plant , the liquid level of the upper pool lying above the liquid level of the lower pool , the system comprising:a conveyor tube having an upper end at the upper pool and a lower end at the lower pool and extending between the upper and lower ends at an acute angle to the vertical;a transport basket movable internally along the tube and into which at least one of the fuel elements can be placed for transfer through the conveyor tube;a fully closing blocking element at one end of the tube that can fully close the conveyor tube at the respective end;a cable hoist having a traction cable guided through the conveyor tube for raising and lowering the transport basket through the conveyor tube; andan intermediate partially closing blocking element offset from the fully closing blocking element in the tube, movable between an open position allowing the basket to pass and a closed position blocking such passage, and formed with a cable passage through which the traction cable can pass in the closed position.2. The system according to claim 1 , wherein the fully closing blocking element is ...

APPARATUS FOR HANDLING FUEL ELEMENTS

A system for transfer of fuel elements between an upper pool and a lower pool of a nuclear plant has a conveyor tube having an upper end in the upper pool and a lower end in the lower pool, formed below the upper end with a laterally open port, and extending between the ends at an acute angle to the vertical. A transport basket into which the fuel elements can be placed can be moved through the conveyor tube by a cable hoist having a cable winch outside the tube and a traction cable guided through the conveyor tube and out of the port and extending along and inside the tube. An upper blocking element can close the upper end of the conveyor tube. The cable port is preferably formed by a lateral hole in the conveyor tube preferably provided directly below the upper blocking element. 1. A system for transfer of fuel elements between an upper pool and a lower pool of a nuclear plant , the system comprising:a conveyor tube having an upper end opening into the upper pool and a lower end opening into the lower pool, formed below the upper end with a laterally open port, and extending between the ends at an acute angle to the vertical;a transport basket into which at least one of the fuel elements can be placed for transport through the conveyor tube;a cable hoist having a cable winch outside the tube and a traction cable guided through the conveyor tube and out of the port and extending along and inside the tube for raising and lowering the transport baskets through the conveyor tube; and,an upper blocking element for closing off the upper end of the conveyor tube.2. The system defined in claim 1 , wherein a liquid level of the upper pool is above a liquid level of the lower pool.3. The system defined in claim 2 , wherein the cable port is formed by a lateral hole in the conveyor tube below the upper blocking element.4. The system defined in claim 1 , further comprising:a cable guide tube extending laterally from the conveyor tube at the cable port and communicating with ...

METHOD AND APPARATUS FOR INSPECTING A FUEL ASSEMBLY

A fuel assembly inspection system that utilizes a pressure transducer mounted to a utility's spent fuel handling tool to detect a relative change in depth of a fuel assembly during fuel inspections. The system then wirelessly transmits the signal to a fuel inspection recording system, which converts the signal to a relative height along the fuel assembly being viewed by a camera, and displays the relative height along with the applicable fuel assembly feature being viewed by the camera (e.g., nozzle, grid, span) via a text overlay on the video image of the inspection. 1. A method of remotely inspecting a nuclear fuel assembly stored in a cell within a rack in a lower portion of a spent fuel pool , the method comprising the steps of:supporting a camera within the spent fuel pool above the rack focused above the cell in which the nuclear fuel assembly is stored, the camera having an output which is transmitted to a processing apparatus outside of the spent fuel pool;fastening a pressure transducer to a long handled fuel assembly handling tool at a fixed distance above a connector on the fuel assembly handling tool that attaches to the fuel assembly and below a point on the fuel assembly handling tool that will remain submerged within the spent fuel pool when the fuel assembly handling tool raises the fuel assembly substantially completely out of the rack, the pressure transducer having an output representative of the depth within the spent fuel pool at the pressure transducer elevation, which pressure transducer output is transmitted to the processing apparatus;lowering the connector to the fuel assembly;attaching the connector to the fuel assembly;raising the fuel assembly out of the cell with the fuel assembly handling tool as the camera records a portion of the fuel assembly in view of the camera and transmits an image of the portion of the fuel assembly in view as at least part of the camera output to the processing apparatus;correlating, in the processing ...

METHOD FOR REFUELING A NUCLEAR REACTOR HAVING AN INSTRUMENTATION PENETRATION FLANGE

A method for retracting in-core instrument thimble tubes from the reactor core prior to refueling a nuclear reactor with top mounted instrumentation. The apparatus includes a penetration flange interposed between the head flange and the reactor vessel flange through which the instrumentation cabling passes. The penetration flange is connected to the upper internals and is raised relative thereto to retract instrumentation thimbles from the core prior to removal of the upper internals from the reactor vessel for refueling. The penetration flange is removed from the vessel with the upper internals. 1. A method of refueling a nuclear reactor comprising:an elongated reactor vessel enclosed at a lower end and having an open upper end on which an annular flange is formed and a central axis extending along an elongated dimension;a reactor vessel head having an annular portion on an underside of the head that is machined to form a sealing surface;a first removable annular seal ring, sized to seat on the reactor vessel flange between the flange and the sealing surface on the underside of the reactor vessel head, the seal ring being interposed between the sealing surface on the underside of the vessel head and the flange on the reactor vessel and having a thickness sized to sealably accommodate one or more radial passages through which one or more instrument conduits pass from outside of the reactor vessel to an interior thereof to communicate instrumentation signals out of a core of the nuclear reactor, the core comprising a plurality of fuel assemblies;an upper internals package supported above the core within the reactor vessel and having a plurality of hollow support columns respectively having a substantially vertical passage therethrough, that extends through and between an upper core plate and an upper support plate of the upper internals package, the passage through the upper core plate being aligned with a corresponding instrument thimble within one of the fuel ...

NUCLEAR REACTOR REFUELING METHODS AND APPARATUSES

Refueling of a nuclear reactor () includes removing a fuel assembly (). The removal method includes lowering a lifting tool () of a crane () onto a top of the fuel assembly. The lowered lifting tool including a plurality of downwardly extending elements () that surround and vertically overlap a portion () of a control rod assembly () extending above the top of the fuel assembly. The downwardly extending elements are locked with corresponding mating features () at the top of the fuel assembly to connect the lifting tool with the fuel assembly. The connected fuel assembly is moved into a spent fuel pool () using the crane, and the lifting tool is disconnected from the top of the fuel assembly by unlocking the downwardly extending elements from the corresponding mating features at the top of the fuel assembly. 1. A method of refueling a nuclear reactor comprising: connecting a lifting tool of a crane with a plurality of lifting pins of the fuel assembly, each lifting pin being non-rotatably affixed to an upper nozzle plate of the fuel assembly and extending upwardly therefrom, the lifting tool comprising a plurality of downwardly extending bars, wherein each of the downwardly extending bars has an upper portion and a lower portion capable of circumferential rotation independent of both the upper portions and the other downwardly extending bars, the connecting including forming a bayonet connection by lowering the downwardly extending bars over the lifting pins so that the lifting pins are disposed within the lower portions of the downwardly extending bars and circumferentially rotating only the lower portion of each of the downwardly extending bars to create a mating connection between each of the downwardly extending bars and the lifting pin over which each of the downwardly extending bars was lowered;', 'moving the fuel assembly connected with the lifting tool into a spent fuel pool using the crane; and', 'releasing the lifting tool from the top of the fuel assembly, ...

GRIPPER WITH DAMPING SYSTEM FOR GRIPPING A FUEL ELEMENT

A gripper a fuel element, comprises a housing, an inner part arranged inside the housing, the inner part and the housing being displaceable relative to one another in an axial direction, with the inner part movable between a first end position and a second end position, a catch member movable between a gripping position and a release position, gripper spring between the housing inner part counteracting movement of the inner part from the second end position, or an intermediate position (Z) between the first and second end position, to the first end position, and a damping system comprising a first and second connecting member for connecting the damping system to the housing, inner part and/or the fuel element loading machine, and a spring member arranged on the first and/or the second connecting member counteracting movement of the inner part from an intermediate position (Z) to the second end position. 1. A gripper for gripping a fuel element , comprisinga housing for fastening the gripper to a fuel element loading machine,an inner part arranged inside the housing, the inner part and the housing being arranged to be displaceable relative to one another in an axial direction such that the inner part is movable between a first end position and a second end position,at least one catch member movable between a gripping position and a release position,a gripper spring arranged between the housing and the inner part, which counteracts a movement of the inner part relative to the housing from the second end position, and/or an intermediate position (Z) located in an axial direction between the first end position and the second end position, to the first end position, anda damping system for damping an overload at the gripper and/or the fuel element loading machine, said damping system comprising at least a first connecting member for connecting the damping system to the housing of the gripper and a second connecting member for connecting the damping system to the inner ...

Method and device for unlatching control rod drive shafts in pressurized water reactors

An unlatching tool configured for actuating a movable section of a control rod drive shaft in a pressurized water reactor includes a base; a gripper assembly configured for gripping the movable section of the control rod drive shaft; a rod movably connecting the gripper assembly to the base; and a mechanical actuator fixed to the base and configured for rotating the rod to raise and lower the gripper assembly. A method for actuating a movable section of a control rod drive shaft includes installing an unlatching tool on the control rod drive shaft; latching the unlatching tool to a stationary section of the control rod drive shaft; and raising a rod connected to a gripper assembly to cause the gripper assembly to grip the movable section and move the movable section upward.

SYSTEMS AND METHODS FOR UNDERWATER TOOL POSITIONING

Systems and methods position tools about a flooded nuclear reactor during maintenance outages without overhead support or alignment structures being necessary. systems may include annular clamps for support from a reactor steam dam, a telescoping mast, a motor or other drive to extend or retract the mast, and/or an articulator to hold the payload and move the same about any degree of freedom. The telescoping mast may include several nested sections joined to a drive motor. Several different articulators are useable, including those with separate gearings for rotation about perpendicular axes and self-leveling wrists to orient tools in confirmed positions. Systems can be locally or remotely powered and controlled through powered and communicative connections to move about any position in a reactor annulus or core. 1. An assembly for positioning a payload in a nuclear reactor annulus , wherein the assembly comprises:an extendible shaft configured to join to an annular vehicle;a motor coupled to the shaft and configured to drive extension and retraction in the shaft; andan articulator secured to an end of the shaft and configured to hold a tool, wherein the assembly lacks any weight support or alignment structure vertically above the shaft and motor.2. The assembly of claim 1 , wherein the articulator is configured to rotate the tool independently about two axes.3. The assembly of claim 2 , wherein the articulator includes a central axis about witch the articulator can rotate itself and the tool claim 2 , and wherein the articulator includes a horizontal axis perpendicular to the central axis about which the articulator can rotate itself and the tool.4. The assembly of claim 2 , wherein the articulator includes a center post rotatably coupled to a center gear claim 2 , and wherein the articulator includes a bevel carrier rotatable coupled to the center post.5. The assembly of claim 4 , wherein the articulator further includes an offset plate rotatable with respect to a ...

Fuel assembly for boiling water reactor

A fuel assembly for a boiling water reactor, having fuel rods, a tie plate, a handle device, and at least two water rods attached to the tie plate and to the handle device. A plurality of spacers, define first passages for some of the fuel rods, and second passages for the water rods. Each water rod comprises a tube part attached to the tie plate, and a solid part attached to the handle device. The tube part permits a flow of coolant. The spacers include primary spacers and a secondary spacer. The primary spacers are attached to the tube parts. The tie plate, the water rods, the primary spacers and the handle device form a support structure carrying the weight of the fuel rods. The secondary spacer is positioned at the solid part of the respective water rod.

FUEL ASSEMBLY FOR A NUCLEAR BOILING WATER REACTOR

A fuel assembly for a nuclear power boiling water reactor, including: a fuel channel defining a central fuel channel axis, fuel rods, each having a central fuel rod axis, at least 3 water channels for non-boiling water, each water channel having a central water channel axis and each water channel having a larger cross-sectional area than the cross-sectional area of (the average) fuel rod. The fuel rods comprise a first group of full length fuel rods and a second group of shorter fuel rods. The fuel assembly comprises at least 5 fuel rods which belong to said second group and which are positioned such that the central fuel rod axis of each of these at least 5 fuel rods is closer to the central fuel channel axis than any of the water channel axes of the water channels. 115-. (canceled)16. A fuel assembly for a nuclear power boiling water reactor , comprising:a fuel channel extending in and defining a length direction of the fuel assembly and defining a central fuel channel axis extending in said length direction;fuel rods positioned such that they are surrounded by said fuel channel, each fuel rod having a central fuel rod axis extending substantially in said length direction; andwater channels positioned such that they are surrounded by said fuel channel, the water channels being configured and positioned for, during operation, allowing non-boiling water to flow through the water channels, each water channel having a central water channel axis extending substantially in said length direction,wherein said fuel rods comprise a first group of fuel rods and a second group of fuel rods,wherein each fuel rod in said first group is a so-called full length fuel rod which extends from a lower part of the fuel assembly to an upper part of the fuel assembly,wherein each fuel rod in said second group extends from said lower part of the fuel assembly and upwards, but does not reach as high up as said full length fuel rods,wherein said water channels of the fuel assembly comprise ...

Gripper mechanism

A gripper mechanism for moving an object having a surface cavity, the gripper mechanism comprising an actuation end moveable in an axial direction and a rotary body. A first mechanism is configured such that movement of the actuation end in an axial direction rotates the rotary body. A gripper is moveable between an engaged position and a disengaged position. In the engaged position the gripper is capable of engaging an object and in the disengaged position the gripper is capable of being received into and removed from a cavity of an object. The gripper is connected to the rotary body by a second mechanism. The second mechanism is configured such that rotary motion of the body moves the gripper between the engaged position and the disengaged position.

Fuel Assembly For An SFR Nuclear Reactor, Comprising A Housing Containing A Removably Fastened Upper Neutron Shielding Device

Fuel assembly for a nuclear reactor comprising a housing of longitudinal axis (X) having a central section containing nuclear-fuel pins and an upper section, forming a portion of the head of the assembly, containing a upper neutron shielding device (NSD) including neutron absorbers and means for reversibly interlocking with the housing and a moveable weight forming the head of the NSD, which is mounted so as to be able to move translationally relative to the rest of the NSD over a given path, said interlocking means being configured so that the NSD and the housing can be interlocked and uninterlocked by moving the moveable weight along the longitudinal axis by means of a grapple for extraction of the NSD, the claws of this grapple engaging with the moveable weight and the rest of the NSD being in downward longitudinal abutment in the interior of the housing. 1. A fuel assembly for nuclear reactor , in particular for sodium-cooled SFR reactor , including:a shroud of longitudinal axis intended to be inserted vertically into the diagrid of the core of the reactor, the shroud comprising a central section housing nuclear fuel rods and an upper section forming the head of the assembly housing an upper neutron shield (UNS) device including neutron absorbers,means for reversibly locking with the shroud and;a weight forming a section of the head of the UNS,wherein said section are translationally movable with respect to the rest of the UNS over a given course,wherein said locking means are configured so that the UNS and the shroud can be locked and unlocked by moving the weight along the longitudinal axis by means of a UNS-extracting gripper with the fingers of the gripper hooked into the weight and the rest of the UNS being in downward longitudinal abutment in the interior of the shroud.2. The fuel assembly as claimed in claim 1 , the head of the assembly furthermore including holes or a groove that is or are suitable for interacting with the fingers of a handling gripper ...

SYSTEM FOR TRANSFERRING FUEL ELEMENTS IN A NUCLEAR POWER PLANT

A system for transferring fuel elements between an upper pool and a lower pool of a nuclear plant has a conveyor tube having an upper end in the upper pool and a lower end in the lower pool, formed below the upper end with a laterally open port, and extending between the ends at an acute angle to the vertical. A transport basket into which the fuel elements can be placed can be moved through the conveyor tube by a cable hoist having a cable winch outside the tube and a traction cable guided through the conveyor tube and out of the port and extending along and inside the tube. An upper blocking element can close the upper end of the conveyor tube. The cable port is preferably formed by a lateral hole in the conveyor tube preferably provided directly below the upper blocking element. 1. In combination with an upper pool and a lower pool of a nuclear power plant , a system for transferring fuel elements between the upper pool and the lower pool , the system comprising:a conveyor tube having an upper end opening into the upper pool and a lower end opening into the lower pool, the tube being formed below the upper end with a laterally open cable port, the tube extending between the ends at an acute angle to the vertical;a transport basket into which at least one of the fuel elements can be placed for transport through the conveyor tube;a cable hoist having a cable winch outside the tube and a traction cable guided through the conveyor tube and out of the cable port and extending below the port along and inside the tube for raising and lowering the transport basket through the conveyor tube; andan upper blocking element above and adjacent the cable port for closing off the upper end of the conveyor tube.2. The combination defined in claim 1 , wherein a liquid level of the upper pool is above the upper blocking element claim 1 , the cable port claim 1 , and a liquid level of the lower pool.3. The combination defined in claim 2 , wherein the cable port is formed by a ...

BOILING WATER REACTOR BLADE GUIDE AND EXCHANGE TOOL

A combined blade guide and exchange tool, include a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of lower collet housings at a lower end of the blade guide tool. A pair of fuel support grapple actuating rods are supported between the plurality of frame rails and have a first end engaging a pair of collets within the pair of lower collet housings and a second end disposed at the upper end of the blade guide tool. A blade exchange tool is releasably mounted to the upper end of the blade guide tool and includes a pair of upper collets for engaging the pair of fuel support grapple actuating rods. The blade exchange tool further including a slider and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging a control rod. 1. A combined blade guide and exchange tool , comprising:a blade guide tool having a lower end and an upper end and a plurality of frame rails supporting a pair of collet housings at a lower end of the blade guide tool, a pair of fuel support grapple actuating rods are supported between the plurality of frame rails and having a first end engaging a pair of collets within the pair of collet housings and having a second end disposed at the upper end of the blade guide tool; anda blade exchange tool releasably mounted to the upper end of the blade guide tool and including a pair of upper collets for engaging the pair of fuel support grapple actuating rods, the blade exchange tool further including a trolley and hook assembly attached to a cable guided by the blade exchange tool and adapted for engaging and lifting a control rod.2. The combined blade guide and exchange tool according to claim 1 , further comprising:a pair of air cylinders connected to respective ones of the pair of upper collets.3. The combined blade guide and exchange tool according to claim 2 , further comprising:a fuel support pin actuating rod adapted to engage a pin on a core support, the fuel ...

System for Separating and Coupling Top Nozzle of Nuclear Fuel Assembly

Disclosed is a system for separating and coupling a top nozzle of a nuclear fuel assembly. There is provided a lock insert configured to support the top nozzle of the nuclear fuel assembly by being coupled to a guide hole provided in a flow channel plate of the top nozzle, the lock insert including: a body in a hollow shape; and an insertion part provided on a top portion of the body and inserted into the guide hole, wherein a circumference of the insertion part is variable in size, thereby being capable of being inserted into the guide hole. Accordingly, disassembly and reassembly of the top nozzle of the nuclear fuel assembly and the lock insert are simplified, thereby simplifying and reducing the number of processes involved therein. Accordingly, the system is effective for maintenance and repair of the nuclear fuel assembly.

UPPER VESSEL TRANSPORT

A system for refueling a nuclear reactor is provided. The system includes a lower reactor vessel with a plurality of fuel rods and a plurality of control rods disposed therein, the lower reactor vessel further comprising an upper flange. An upper reactor vessel is provided which encloses a steam generator and a pressurizer, the upper reactor vessel further comprising a lower flange that matingly engages the upper flange of the lower reactor vessel. A transporter surrounds an outer surface of the upper reactor vessel, wherein the transporter is configured to translate the upper reactor vessel vertically toward and away from the lower reactor vessel and also to translate the upper reactor vessel horizontally toward or away from alignment with the lower reactor vessel. 1. A system for refueling a nuclear reactor , comprising:a lower reactor vessel comprising a plurality of fuel rods and a plurality of control rods disposed therein, the lower reactor vessel further comprising an upper flange;an upper reactor vessel comprising a steam generator and pressurizer disposed therein, the upper reactor vessel further comprising a lower flange that matingly engages the upper flange of the lower reactor vessel; anda transporter surrounding an outer surface of the upper reactor vessel, wherein the transporter includes a collar surrounding the outer surface of the upper reactor vessel, the collar including first and second wheels affixed thereto that are disposed upon respective first and second horizontal tracks, the first and second horizontal tracks being parallel to each other, and one or more of hydraulically-operated and electrically-operated lifts, each lift being secured to the collar and extendable upwardly to engage the upper reactor vessel and translate the upper reactor vessel vertically toward or away from the lower reactor vessel, and the transporter translates the upper reactor vessel horizontally toward or away from vertical alignment with the lower reactor vessel, ...

Apparatus for pressing-in and pressing-out steady pin under pressure

FIELD: physics. SUBSTANCE: invention relates to apparatus (40) used to press-in and press-out a steady pin (2) under pressure, having a first socket (52) lying opposite a head (56) for pressing-in, which is movably fixed in the housing (42) of the apparatus; a second socket (76) lying opposite a head (78) for pressing-out, which is also movably fixed in the housing (42); and a means (100) for creating pressure, which can rotate in the housing (42), capable for switching from a press-in position, where it can exert pressure on the head for pressing-in, to press-out position, where it can exert pressure on the head for pressing-out, and vice-versa. EFFECT: design of apparatus which enables pressing-in and pressing-out of a pin under pressure. 15 cl, 10 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) 2 452 049 (13) C2 (51) МПК G21C 19/00 (2006.01) B23P 19/04 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (21)(22) Заявка: 2009129519/07, 28.12.2007 (24) Дата начала отсчета срока действия патента: 28.12.2007 (73) Патентообладатель(и): АРЕВА НС (FR) R U Приоритет(ы): (30) Конвенционный приоритет: 03.01.2007 FR 0752518 (72) Автор(ы): БАРР Дидье (FR) (43) Дата публикации заявки: 10.02.2011 Бюл. № 4 2 4 5 2 0 4 9 (45) Опубликовано: 27.05.2012 Бюл. № 15 (56) Список документов, цитированных в отчете о поиске: SU 1637997 A1, 30.03.1991. RU 2158383 C1, 27.10.2000. RU 2265500 C2, 10.12.2005. EP 0636459 A1, 01.02.1995. US 2003084555 A1, 08.05.2003. 2 4 5 2 0 4 9 R U (86) Заявка PCT: EP 2007/064611 (28.12.2007) C 2 C 2 (85) Дата начала рассмотрения заявки PCT на национальной фазе: 03.08.2009 (87) Публикация заявки РСТ: WO 2008/080967 (10.07.2008) Адрес для переписки: 103735, Москва, ул. Ильинка, 5/2, ООО "Союзпатент", пат.пов. С.Б.Фелицыной, рег. № 303 (54) УСТРОЙСТВО ДЛЯ ЗАПРЕССОВКИ И ВЫПРЕССОВКИ ПОД ДАВЛЕНИЕМ ЗАЖИМНОГО ШТИФТА (57) Реферат: Изобретение относится к устройству (40), применяемому для запрессовки и выпрессовки под давлением ...

Device for loading and unloading fuel elements of nuclear reactor core

FIELD: transportation.SUBSTANCE: invention relates to handling devices and can be used in handling devices of nuclear reactors at loading and unloading of fuel elements. Device for loading and unloading of fuel elements of core of nuclear reactor comprises rod and spring. Device is additionally equipped with a collet made in the form of a guiding bushing and an even number of lobes, a handle, a clamp and two ropes. On the rod there are radial holes, through which by means of pins the handle and clamp are connected to the first rope by means of loops, and diametrically opposite slots. Collet is fixed on the rod by means of a pin and forms a step for the spring stop in the place of connection with the bar, which is installed on the guide bushing between the butt end of the rod and the butt end of the clamp. First rope is located inside the rod and the guide bushing, and on the outer surface of the rod – between the handle and the clamp – a groove is made for passage of the second rope forming a safety loop fixed by the clamping bushing.EFFECT: invention simplifies the design of the device.1 cl, 2 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 725 759 C1 (51) МПК G21C 19/10 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/10 (2020.02) (21)(22) Заявка: 2020101161, 10.01.2020 (24) Дата начала отсчета срока действия патента: 06.07.2020 Приоритет(ы): (22) Дата подачи заявки: 10.01.2020 (45) Опубликовано: 06.07.2020 Бюл. № 19 2 7 2 5 7 5 9 R U (54) Устройство для загрузки и выгрузки твэлов активной зоны ядерного реактора (57) Реферат: Изобретение относится к грузозахватным диаметрально противоположные пазы. Цанга устройствам и может найти применение в закреплена на штанге с помощью штифта и перегрузочных устройствах ядерных реакторов образует в месте сопряжения со штангой при загрузке и выгрузке тепловыделяющих ступеньку для упора пружины, которая элементов (твэл). Устройство для загрузки и установлена на ...

Control rod grabbing mechanism for nuclear power station

本发明属于一种抓取机构，具体公开一种核电站用控制棒抓取机构。包括接头、与接头连接的连接套、与连接套固定连接的拉杆、位于拉杆外部的外套筒、位于外套筒内部的内套筒、固定于内套筒上的推杆、固定于外套筒下端的端盖II、固定于端盖II上可以转动的抓头，所述的拉杆位于内套筒内侧；所述的内套筒与推杆间连接有顶针；所述的拉杆下端固定有单向转动的星形轮；所述的拉杆侧壁有用于放置钢珠的梯形凹槽；所述内套筒侧壁有用于放置钢珠的通孔；所述外套筒侧壁有用于放置钢珠的锥形凹槽；所述外套筒上端有端盖I。该装置有效消除了原先无法正常抓取、脱开的固有缺陷，不仅在对比试验台架上得到了验证，大大降低了换棒所需的时间。

Container for discharge of spent fuel assemblies

Изобретение относится к атомной энергетике, в частности к устройствам для обращения с отработавшим ядерным топливом, а более конкретно к контейнерам, в которых размещаются отработавшие тепловыделяющие сборки (ОТВС). Контейнер для выгрузки отработавших тепловыделяющих сборок содержит шибер и захват. Шибер и захват имеют независимый электромеханический и ручной привод каждый. Шибер выполнен в виде усеченного конуса с резиновым покрытием, ось которого перпендикулярна оси контейнера. Захват снабжен электромагнитами. Электромагниты соединены трос-кабелем через блок с электромеханическим приводом. Изобретение позволяет размещать в контейнере ОТВС различных типов, а также пеналы с фрагментами ОТВС, расцеплять захват при заедании ОТВС с измененными геометрическими параметрами в хранилище, транспортировать ОТВС со стекающими ЖРО. 5 з.п. ф-лы, 8 ил. РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 622 901 C2 (51) МПК G21C 19/00 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ФОРМУЛА (21)(22) Заявка: ИЗОБРЕТЕНИЯ К ПАТЕНТУ РОССИЙСКОЙ ФЕДЕРАЦИИ 2015142521, 06.10.2015 (24) Дата начала отсчета срока действия патента: 06.10.2015 Дата регистрации: Приоритет(ы): (22) Дата подачи заявки: 06.10.2015 (43) Дата публикации заявки: 10.04.2017 Бюл. № 10 Адрес для переписки: 603074, г. Нижний Новгород, Бурнаковский прд, 15, АО "ОКБМ Африкантов" (56) Список документов, цитированных в отчете о поиске: RU 2313837 C1, 27.12.2007. RU 2323493 C1, 27.04.2008. RU 2030802 C1, 10.03.1995. US 6359953 B1, 19.03.2002. US 6295329 B1, 25.09.2001. 2 6 2 2 9 0 1 R U (57) Формула изобретения 1. Контейнер для выгрузки отработавших тепловыделяющих сборок, содержащий шибер и захват, каждый с независимыми электромеханическим и ручным приводами, отличающийся тем, что шибер выполнен в виде усеченного конуса с резиновым покрытием, ось которого перпендикулярна оси контейнера, а захват снабжен электромагнитами, соединенными трос-кабелем через блок с электромеханическим приводом. 2. Контейнер по п. 1, ...

Apparatus for gripping and transporting a fuel element

Изобретение относится к области ядерной энергетики, в частности к устройствам для захвата тепловыделяющих элементов, устанавливаемым на промышленных роботах манипуляторах. Устройство содержит: базовую опору, тягу, продольную опору, вилку, выполненную с возможностью по меньшей мере частичного размещения в ней тепловыделяющего элемента, опорную площадку, установленную в нижней части базовой опоры, рычажную систему, и по меньшей мере две губки захвата, содержащие по меньшей мере два сжимающих компонента. Рычажная система выполнена с возможностью обеспечения раскрытия губок захвата, а в нижней части тяги установлен толкатель. При перемещении тяги в одном из направлений вдоль базовой опоры обеспечена передача движения на рычажную систему для раскрытия губок захвата. При перемещении вертикальной тяги в противоположном направлении обеспечена передача движения на рычажную систему для закрытия губок захвата для захвата и транспортировки тепловыделяющего элемента. Изобретение позволяет эффективно использовать пассивную механику без пневматики конструктивно сложных узлов и деталей, с обеспечением передачи твэла, как в горизонтальном, так и в вертикальном положении. 5 з.п. ф-лы, 9 ил. РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 759 051 C1 (51) МПК G21C 19/10 (2006.01) G21C 19/105 (2006.01) G21C 19/18 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/105 (2021.08) (21)(22) Заявка: 2020128679, 28.08.2020 (24) Дата начала отсчета срока действия патента: Дата регистрации: (73) Патентообладатель(и): Акционерное общество «Прорыв» (RU) 09.11.2021 (56) Список документов, цитированных в отчете о поиске: RU 2488902 C2, 27.07.2013. RU 2725759 C1, 06.07.2020. SU 634696 A3, 25.11.1978. US 4311557 A, 19.01.1982. (45) Опубликовано: 09.11.2021 Бюл. № 31 2 7 5 9 0 5 1 R U (54) Устройство для захвата и транспортировки тепловыделяющего элемента (57) Реферат: Изобретение относится к области ядерной перемещении тяги в одном из ...

Vehicle-mounted mobile material changing system and material changing method

本发明提供了一种车载移动式换料系统及换料方法，包括换料集装箱、升降系统、移动系统和驱动系统；换料集装箱具体为一长方体箱体，箱体内部设有遥操拆卸机构、遥操换料机构、新燃料储存池、乏燃料储存池和顶盖临时搁置架，箱体的底端开有转运通道，转运通道上装有密封件；换料集装箱的顶部内壁上还设有横置轨道，遥操拆卸机构与遥操换料机构通过横置轨道与换料集装箱的顶部滑动相连，并沿轨道方向水平移动。本发明还提供了一种车载移动式换料系统的换料方法。本发明的优点在于：将换料过程所需的开关盖、装卸料、乏燃料回收等功能耦合在一个可移动的封闭集装箱内，可自行驶或被运输至任意换料需求地，从而灵活、便捷地完成闭式换料任务。

Control rod handling device and method

A nuclear fuel road end gap adjusting device

본 발명은 핵연료봉 끝단 간격 조정장치에 관한 것으로서, 더욱 상세하게는 회전운동의 직진운동 변화에 따른 장입동력수단의 구성을 통해 장입봉의 이동길이 조정이 더욱 세밀하게 이루어질 수 있도록 하되, 장입동력수단의 회전운동은 장입봉에 전달되지 않도록 함으로써 핵연료봉의 끝단 간격 조정이 안정적으로 이루어질 수 있도록 한 핵연료봉 끝단 간격 조정장치에 관한 것이다. 이를 위해, 핵연료봉 집게를 포함하며, 전,후 직진 이동되는 장입봉;중공(中空)의 하우징;상기 하우징의 내측에 설치되며, 회전 운동을 직진 운동으로 변환하여 하우징의 길이 방향으로 이동되는 장입동력수단;상기 장입동력수단과 상기 장입봉 사이에 연결된 커넥터;상기 장입동력수단과 커넥터 사이에 설치되며, 상기 장입동력수단의 직진운동과 연동되어 하우징의 길이 방향으로 이동이 이루어지되, 장입동력수단의 회전력이 커넥터에 전달되는 것을 방지하는 회전방지구:를 포함하여 구성된 핵연료봉 끝단 간격 조정장치를 제공한다. The present invention relates to a nuclear fuel rod end spacing adjusting device, and more specifically, to adjust the moving length of the charging rod through the configuration of the charging power means according to the change in the linear movement of the rotational movement, The rotational movement relates to a nuclear fuel rod end gap adjusting device which is configured to stably adjust the nuclear fuel rod end gap by preventing it from being transmitted to the charging rod. To this end, the rod including the nuclear fuel rod tongs, the charging rod is moved straight ahead; the housing of the hollow; (hollow) housing; is installed inside the housing, the charging is moved in the longitudinal direction of the housing by converting the rotational movement into a straight movement A connector connected between the charging power means and the charging rod; installed between the charging power means and the connector, interlocked with the straight motion of the charging power means, and moving in the longitudinal direction of the housing, the charging power means It provides a nuclear fuel rod end spacing device configured to include a rotation prevention device: to prevent the rotational force of the transmission to the connector.

Unloading and loading device for the fuel rod array and unloading and loading node containing such a device

FIELD: mechanical engineering,SUBSTANCE: invention relates to the field of loading fuel assemblies, namely to the unloading and loading device and to the node containing the unloading and loading device. The unloading and loading device for the heat-generating assembly contains a housing; capture means capable of interacting with the heat-generating assembly so as to capture or release the said assembly; control means for controlling the capture means capable of controlling the said capture means between the capture position and the release position of the said assembly, and vice versa; suction means capable of creating suction of cooling gas through the unloading and loading device and through the assembly when it is captured by the said device.EFFECT: invention is able to function autonomously at elevated temperatures.17 cl, 29 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 764 463 C1 (51) МПК G21C 19/04 (2006.01) G21C 19/105 (2006.01) G21C 19/32 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/04 (2021.08); G21C 19/105 (2021.08) (21)(22) Заявка: 2021104300, 10.07.2019 (24) Дата начала отсчета срока действия патента: (73) Патентообладатель(и): СЕЙВ (FR) Дата регистрации: 17.01.2022 24.07.2018 FR 1856822 (45) Опубликовано: 17.01.2022 Бюл. № 2 (85) Дата начала рассмотрения заявки PCT на национальной фазе: 24.02.2021 (86) Заявка PCT: 2 7 6 4 4 6 3 R U (87) Публикация заявки PCT: WO 2020/020641 (30.01.2020) Адрес для переписки: 129090, Москва, ул. Б. Спасская, 25, стр. 3, ООО "Юридическая фирма Городисский и Партнеры" (54) РАЗГРУЗОЧНО-ЗАГРУЗОЧНОЕ УСТРОЙСТВО ДЛЯ ТЕПЛОВЫДЕЛЯЮЩЕЙ СБОРКИ И РАЗГРУЗОЧНО-ЗАГРУЗОЧНЫЙ УЗЕЛ, СОДЕРЖАЩИЙ ТАКОЕ УСТРОЙСТВО (57) Реферат: Изобретение относится к области загрузки упомянутыми средствами захвата между тепловыделяющих сборок, а именно к положением захвата и положением разгрузочно-загрузочному устройству и к узлу, высвобождения упомянутой сборки, и наоборот; содержащему ...

Container for unloading spent fuel assemblies

РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2015 142 521 A (51) МПК G21C 19/00 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ЗАЯВКА НА ИЗОБРЕТЕНИЕ (21)(22) Заявка: 2015142521, 06.10.2015 Приоритет(ы): (22) Дата подачи заявки: 06.10.2015 (43) Дата публикации заявки: 10.04.2017 Бюл. № 10 R U (57) Формула изобретения 1. Контейнер для выгрузки отработавших тепловыделяющих сборок, содержащий шибер и захват, каждый с независимыми электромеханическим и ручным приводами, отличающийся тем, что шибер выполнен в виде усеченного конуса с резиновым покрытием, ось которого перпендикулярна оси контейнера, а захват снабжен электромагнитами, соединенными трос-кабелем через блок с электромеханическим приводом. 2. Контейнер по п. 1, отличающийся тем, что захват снабжен электромагнитным механизмом запирания захвата с блокировкой запирания при отключении питания. 3. Контейнер по п. 1, отличающийся тем, что он снабжен весоизмерительным устройством. 4. Контейнер по п. 1, отличающийся тем, что ручные приводы снабжены конечными индуктивными выключателями. 5. Контейнер по п. 1, отличающийся тем, что между ручным приводом шибера и его электромеханическим приводом установлена разъединительная муфта. 6. Контейнер по п. 1, отличающийся тем, что в нижнем торце контейнера установлен конечный индуктивный выключатель. Стр.: 1 A 2 0 1 5 1 4 2 5 2 1 A (54) Контейнер для выгрузки отработавших тепловыделяющих сборок 2 0 1 5 1 4 2 5 2 1 (72) Автор(ы): Душев Сергей Анатольевич (RU), Шапкин Владимир Иванович (RU), Данилов Сергей Дмитриевич (RU), Коновалов Дмитрий Викторович (RU), Постнов Павел Юрьевич (RU) R U Адрес для переписки: 603074, г. Нижний Новгород, Бурнаковский прд, 15, АО "ОКБМ Африкантов" (71) Заявитель(и): Акционерное общество "Опытное Конструкторское Бюро Машиностроения имени И.И. Африкантова" (АО "ОКБМ Африкантов") (RU)

Device for installation of casing pipe unloading-loading machine

FIELD: machine building.SUBSTANCE: invention relates to nuclear engineering. Device for installation of a casing pipe includes a mandrel, a bracket connected to it by an axis, two stops and neodymium magnets installed on them to provide control of movement of stops and rotation of a mandrel relative to a bracket. At that, the mandrel structure is made with one part with the possibility of rotation on the axis and represents a complex-spatial configuration made in the form of two cylinders of different diameters, matched with each other along one axis and mechanically processed so that in the other projection at angle of 90° they in turn form cylinder with smaller diameter. Mandrel structure is equipped with threaded hole, smooth holes with ledges for supports, slot for bracket and collar for installation of casing pipe on it. Bracket design is equipped with a volumetric convex ledge with a hole for fixation of magnets in it. Device is made with possibility of unfixturing with casing pipe only at action on both stops.EFFECT: invention makes it possible to automatically provide a process of unfixturing with the casing pipe during its installation in the pipe a transition guide.6 cl, 17 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 687 244 C1 (51) МПК G21C 19/10 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/10 (2019.02) (21) (22) Заявка: 2018123429, 27.06.2018 (24) Дата начала отсчета срока действия патента: 27.06.2018 08.05.2019 Приоритет(ы): (22) Дата подачи заявки: 27.06.2018 (45) Опубликовано: 08.05.2019 Бюл. № 13 2484240 C1, 10.06.2013. RU 2569336 C1, 20.11.2015. EP 2617040 B1, 13.05.2015. WO 2012035255 A1, 22.03.2012. (54) Приспособление для установки трубы обсадной разгрузочно-загрузочной машины (57) Реферат: Изобретение относится к области атомного очередь образуют цилиндр с меньшим диаметром. машиностроения. Приспособление для установки Конструкция оправки оснащена резьбовым трубы обсадной ...

Machine for loading of fuel assemblies

FIELD: power engineering. SUBSTANCE: machine (2) for loading of fuel assemblies (FA) includes a guide mast (10) and telescopic elements telescopically lowered from the guide mast (10) and again raised in the form of a centre head (12), a fuel element grab (14) and a control element grab (16). Telescopic elements are engaged to each other and actively connected to a common main lifting mechanism (18) so that whenever telescopic elements are raised from the lowered position, at first the control element grab (16) grabs the fuel assembly grab (14), and then the FA grab (14) grabs the centre head (12). The guide mast (10) is equipped with a fixed stop (22), which sets the final position of the centre head (12), achieved when lowered. On the guide mast (10) there is a stop (40) that moves in the direction (38) of lifting or lowering, and this stop interacts with the appropriate support flange (20) of the centre head (12) so that the centre head (12), when the moved stop (40) is raised, may be raised from its final position to the above intermediate position. EFFECT: reduction of time required to replace a FA and efficient response to possible arising problems of centring. 7 cl, 2 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) 2 495 508 (13) C1 (51) МПК G21C 19/00 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (21)(22) Заявка: 2012107339/07, 21.02.2011 (24) Дата начала отсчета срока действия патента: 21.02.2011 (72) Автор(ы): ВАГНЕР Маттиас (DE), ЛАНГЕ Уве (DE) (73) Патентообладатель(и): АРЕФА НП ГМБХ (DE) R U Приоритет(ы): (30) Конвенционный приоритет: 06.04.2010 DE 102010014039.2 (45) Опубликовано: 10.10.2013 Бюл. № 28 2 4 9 5 5 0 8 (56) Список документов, цитированных в отчете о поиске: US 20040017876 A1, 29.01.2004. SU 397094 A1, 1984.11.07. RU 2319236 C1, 10.03.2008. US 6359953 B1, 19.03.2002. (85) Дата начала рассмотрения заявки PCT на национальной фазе: 28.02.2012 2 4 9 5 5 0 8 R U (87) Публикация заявки РСТ: WO 2011/ ...

Device for gripping and transporting fuel element having annular groove

FIELD: physics. SUBSTANCE: invention relates to nuclear power engineering, in particular, to devices for capturing fuel elements installed on industrial robots-manipulators for performing transport-technological operations, fixation and transfer of fuel element during its assembly and control. Device comprises: a base support, a tie-rod, a fixation device mounted on the longitudinal support and protruding relative to it so that to cover the tie-rod and made with possibility of at least partial fixation of the fuel element in it, a support platform, a lever system and at least two gripping jaws. Lever system is designed so that to enable opening of the gripping jaws, and a pusher is installed in the lower part of the tie-rod. When the rod moves in one of the directions along the base support, the movement is transmitted to the lever system for opening the gripping jaws. When the vertical link moves in the opposite direction, the movement is transmitted to the lever system for closing the gripping jaws for gripping and transporting the fuel element. EFFECT: invention provides the necessary safety and excludes inadmissible damages (distortions) of fuel elements. 9 cl, 10 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 768 793 C1 (51) МПК G21C 19/105 (2006.01) G21C 19/18 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/105 (2021.08) (21)(22) Заявка: 2021100259, 11.01.2021 (24) Дата начала отсчета срока действия патента: 24.03.2022 Приоритет(ы): (22) Дата подачи заявки: 11.01.2021 (56) Список документов, цитированных в отчете о поиске: RU 2488902 C2, 27.07.2013 . RU 2725759 C1, 06.07.2020 . SU 634696 A3, 25.11.1978 . US 4311557 A, 19.01.1982 . (45) Опубликовано: 24.03.2022 Бюл. № 9 2 7 6 8 7 9 3 R U (54) Устройство для захвата и транспортировки тепловыделяющего элемента, имеющего кольцевую проточку (57) Реферат: Изобретение относится к области ядерной захвата. Рычажная система выполнена с энергетики, в ...

DEVICE FOR REMOVING Fallen NUCLEAR REACTOR SUBJECTS

РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2016 151 925 A (51) МПК G21C 19/10 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ЗАЯВКА НА ИЗОБРЕТЕНИЕ (21)(22) Заявка: 2016151925, 28.12.2016 Приоритет(ы): (22) Дата подачи заявки: 28.12.2016 (43) Дата публикации заявки: 02.07.2018 Бюл. № 19 R U (57) Формула изобретения 1. Устройство для извлечения упавших предметов ядерного реактора, содержащее подвижную платформу с грузоподъемным устройством, привод, вертикальную полую штангу, соединенную со средством захвата, включающем лапки захвата, соединенные с поворачиваемыми рычагами шарнирным соединением, отличающееся тем, что дополнительно содержит опорную раму, с размещенным на ней снабженным тросамитягами приводом, которая соединена в верхней части с грузоподъемным устройством, а в нижней части - с неподвижной полой секцией штанги, выполненной телескопической, при этом подвижная секция штанги соединена с тросом-тягой перемещения ее по вертикали и в нижней части соединена со средством захвата, которое включает полый корпус с прорезью, снабженный в нижней ее части общей осью двух рычагов и размещенным внутри соединенным с тросом-тягой подвижным грузом, который в нижней части выполнен с двумя горизонтальными осями, размещенными в пазах двух рычагов на общей оси и поворачивающими рычаги при перемещении подвижного груза, причем лапки захвата, образуют ⊥-образное шарнирное соединения с рычагами и на концах имеют соединение с тросами-тягами для их поворота. 2. Устройство по п. 1, отличающееся тем, что привод выполнен в виде блока, включающего четыре вращаемых барабана с тросами-тягами, соединенными соответственно с подвижной секцией телескопической штанги, с подвижным грузом, с одним концом пары лапок захвата, с другим концом пары лапок захвата. Стр.: 1 A 2 0 1 6 1 5 1 9 2 5 A (54) УСТРОЙСТВО ДЛЯ ИЗВЛЕЧЕНИЯ УПАВШИХ ПРЕДМЕТОВ ЯДЕРНОГО РЕАКТОРА 2 0 1 6 1 5 1 9 2 5 (72) Автор(ы): Тумаков Евгений Алексеевич (RU), Палагин Евгений Александрович (RU), Кульбицкий Евгений ...

Riser transition element for compact nuclear reactor

核反应堆堆芯安置于压力容器中，上部堆内构件安置于压力容器中反应堆堆芯上方。上部堆内构件包括安装到悬挂支承组件上的内部控制棒驱动机构(CRDM)。中空圆柱形中心立管安置于压力容器中核反应堆堆芯上方。中空圆柱形部段安置于压力容器中在中空圆柱形中心立管下方并且包围核反应堆堆芯。立管过渡元件与中空圆柱形中心立管和中空圆柱形部段连接以形成连续中空圆柱形流动分离器。上部堆内构件的悬挂支承组件从立管过渡元件悬挂。压力容器可以包括由中凸缘连接的上容器部段和下容器部段，并且立管过渡元件由角撑板焊接到中凸缘上，角撑板从立管过渡元件向外并且向上延伸到中凸缘。

Gripping and locking/unlocking system and its application for handling holders of samples of nuclear materials

FIELD: machine engineering. SUBSTANCE: gripping and locking/unlocking system is provided by one or more engaging devices ensuring both sealed locking/unlocking of the inner tube together with the gripping element and the inner tube in the outer tube, and it is applied only when the gripping element is moved to displacement A or displacement B. The system is a system for inserting and removing the sample holder tube intended for placing a sample of nuclear materials, for example nuclear fuel, inside and outside the measuring tube of instrument holder intended for placing measurement sensors and the cooling system. EFFECT: invention makes it possible to handle holders of samples of nuclear materials in research nuclear reactor to ensure extraction of holders of samples without any damage in protective shell with respect to external medium, reliable, simple in manufacture and quick in use. 16 cl, 26 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 642 437 C2 (51) МПК G21C 19/00 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ ИЗОБРЕТЕНИЯ К ПАТЕНТУ (52) СПК G21C 19/00 (2006.01) (21)(22) Заявка: 2013152681, 28.11.2013 (24) Дата начала отсчета срока действия патента: (73) Патентообладатель(и): КОМИССАРЬЯ А Л'ЭНЕРЖИ АТОМИК Э ОЗ ЭНЕРЖИ АЛЬТЕРНАТИВ (FR) Дата регистрации: 25.01.2018 (56) Список документов, цитированных в отчете о поиске: FR 2906638 A1, 04.04.2008. SU 04.12.2012 FR 1261578 (43) Дата публикации заявки: 10.06.2015 Бюл. № 16 206732 A1, 05.12.1976. SU 440968 A1, 15.07.1984. US 2005188794 A1, 01.09.2005. JP 8233982 A, 13.09.1996. (45) Опубликовано: 25.01.2018 Бюл. № 3 2 6 4 2 4 3 7 R U (54) ЗАХВАТЫВАЮЩАЯ И БЛОКИРУЮЩАЯ/ДЕБЛОКИРУЮЩАЯ СИСТЕМА И ЕЕ ПРИМЕНЕНИЕ ДЛЯ МАНИПУЛИРОВАНИЯ ДЕРЖАТЕЛЯМИ ОБРАЗЦОВ ЯДЕРНЫХ МАТЕРИАЛОВ (57) Реферат: Изобретение относится к системам для захвата предназначенной для размещения образца внутренней трубки и блокировки/деблокировки ядерных материалов, например, ядерного ее во внешней трубке, концентрической с топлива, ...

Gripping device of nuclear reactor reloading mechanism

DEVICE FOR REMOVING Fallen NUCLEAR REACTOR SUBJECTS

РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2016 151 927 A (51) МПК G21C 19/10 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ЗАЯВКА НА ИЗОБРЕТЕНИЕ (21)(22) Заявка: 2016151927, 28.12.2016 Приоритет(ы): (22) Дата подачи заявки: 28.12.2016 (43) Дата публикации заявки: 28.06.2018 Бюл. № 19 R U (57) Формула изобретения 1. Устройство для извлечения упавших предметов ядерного реактора содержит подвижную платформу с грузоподъемным устройством, привод, вертикальную полую штангу и средство захвата, включающее лапки захвата на нижних концах двух поворачиваемых рычагов, соединенных шарнирно выступами, выполненными в средней части рычагов, причем рычаги шарнирно соединены в верхней части с двумя звеньями, соединенных шарнирно между собой, отличающееся тем, что дополнительно содержит опорную раму, на которой размещен привод, снабженный тросами-тягами, и траверсу с размещенными на ее концах, соединенных с тросами-тягами привода, двух средств захвата, причем опорная рама в верхней части соединена с грузоподъемным устройством, а в нижней части соединена с неподвижной секцией полой штанги, выполненной телескопической, при этом подвижная секция штанги соединена с тросомтягой перемещения ее по вертикали и в нижней части соединена шарнирно со средней частью траверсы, причем каждое средство захвата включает полый корпус с прорезью, в нижней части которого размещена ось шарнирного соединения выступов двух рычагов, и размещенным внутри корпуса соединенным с тросом-тягой подвижным грузом, в нижней части которого размещена ось шарнирного соединения двух звеньев. 2. Устройство по п. 1, отличающееся тем, что привод выполнен в виде блока, включающем вращаемые барабаны с тросами-тягами, соединенными соответственно с подвижной секцией телескопической штанги, с подвижными грузами и с концами траверсы. Стр.: 1 A 2 0 1 6 1 5 1 9 2 7 A (54) УСТРОЙСТВО ДЛЯ ИЗВЛЕЧЕНИЯ УПАВШИХ ПРЕДМЕТОВ ЯДЕРНОГО РЕАКТОРА 2 0 1 6 1 5 1 9 2 7 (72) Автор(ы): Тумаков Евгений Алексеевич (RU), Палагин ...

BWR control rod handling tooling and method

A tool set and a method of using those tools in combination is disclosed that are especially well adapted to the function of rearranging and/or replacing the control rods and fuel supports in a boiling water reactor. The tool set includes a grapple (40) that is capable of simultaneously picking up both a control rod and its associated fuel support. A separate unlatching tool (90) is provided for pulling the control rod's release handle in order to decouple the control rod from a control rod drive. A storage rack (150) that may be mounted in the reactor pressure vessel is provided for storing a fuel support and a pair of control rods when the positions of selected control rods are being shifted about the reactor core area. In the method aspect of the invention, the unlatching tool (90) is used to pull the control rod's release handle. Thereafter, the grapple (40) lifts the control rod and its associated fuel support as a unit. When rearranging the positions of the control rods, a first control rod and its associated fuel support are placed in the storage rack (150). Then a second control rod/fuel support assembly is removed in a similar manner and the second control rod is placed in the storage rack (150). Thereafter, the first control rod may be removed from the storage rack (150) and placed in the position formally occupied by the second control rod, with the same fuel support that was removed from the second location.

Apparatus, system and method of generating particle beams based on electron cyclotron resonance

FIELD: physics. SUBSTANCE: invention relates to an ion source. The apparatus includes a chamber placed around a longitudinal axis and containing a gas, a magnetic confinement system designed to generate a magnetic field in the a confinement region in the chamber, an electron cyclotron resonance exciter which generates an alternating electric field, which excites cyclotron movement of electrons located in the confinement region, wherein the excited electrons interact with the gas to form confined plasma. During operation, the magnetic confinement system confines the plasma in the confinement region. EFFECT: enabling multiple ionising interactions with excited electrons for some atoms in a plasma while enabling formation of multiple-ionised ions, having the chosen final ionisation state. 84 cl, 1 tbl, 17 dwg РОССИЙСКАЯ ФЕДЕРАЦИЯ (19) RU (11) (13) 2 526 026 C2 (51) МПК G21G 4/08 (2006.01) ФЕДЕРАЛЬНАЯ СЛУЖБА ПО ИНТЕЛЛЕКТУАЛЬНОЙ СОБСТВЕННОСТИ (12) ОПИСАНИЕ (21)(22) Заявка: ИЗОБРЕТЕНИЯ К ПАТЕНТУ 2011151095/07, 16.07.2009 (24) Дата начала отсчета срока действия патента: 16.07.2009 (72) Автор(ы): РОЗЕНТАЛЬ Гленн Б. (US) (73) Патентообладатель(и): АЛЬФА СОРС ЭлЭлСи (US) Приоритет(ы): (30) Конвенционный приоритет: (43) Дата публикации заявки: 20.06.2013 Бюл. № 17 R U 15.05.2009 US 61/178,857 (45) Опубликовано: 20.08.2014 Бюл. № 23 15.08.2002. JP2003257329A, 12.09.2003. RU2241278C1, 27.11.2004 (85) Дата начала рассмотрения заявки PCT на национальной фазе: 15.12.2011 (86) Заявка PCT: 2 5 2 6 0 2 6 (56) Список документов, цитированных в отчете о поиске: US5506475,09.04.1996.WO02/063637A, 2 5 2 6 0 2 6 R U (87) Публикация заявки PCT: WO 2010/132068 (18.11.2010) Адрес для переписки: 129090, Москва, ул. Б. Спасская, 25, строение 3, ООО "Юридическая фирма Городисский и Партнеры" (54) УСТРОЙСТВО, СИСТЕМА И СПОСОБ СОЗДАНИЯ ПУЧКОВ ЧАСТИЦ НА ОСНОВЕ ЭЦР (57) Реферат: Изобретение относится к источнику ионов. взаимодействуют с газом, образуя удерживаемую Устройство включает в себя камеру, ...

Electric cartridge grapple

LOCKING / UNLOCKING SYSTEM, APPLICATION TO SAMPLE DOOR HANDLING OF NUCLEAR MATERIALS

La présente invention concerne un système de préhension et de verrouillage/déverrouillage d'un tube intérieur dans un tube extérieur concentrique au tube intérieur. Le système selon l'invention est prévu avec un ou plusieurs dispositifs d'accrochage qui permett(ent) à la fois le verrouillage étanche/déverrouillage du tube intérieur à l'organe de préhension, et du tube intérieur dans le tube extérieur, et ce avec seulement un déplacement en translation de l'organe de préhension selon la course A ou la course B. Le système selon l'invention constitue avantageusement un système d'introduction et d'extraction d'un tube porte-échantillon destiné à loger un échantillon de matériaux nucléaires, tels que des combustibles nucléaires, dans un tube porte-instrumentation de mesure destiné à loger des capteurs de mesure et un système de refroidissement. The present invention relates to a system for gripping and locking / unlocking an inner tube in an outer tube concentric to the inner tube. The system according to the invention is provided with one or more attachment devices which allow (ent) both the sealing / unlocking locking of the inner tube to the gripping member, and the inner tube in the outer tube, and this with only a displacement in translation of the gripping member according to the stroke A or the stroke B. The system according to the invention advantageously constitutes a system for introducing and extracting a sample tube intended to house a sample nuclear materials, such as nuclear fuels, in a measuring instrumentation tube for housing measuring sensors and a cooling system.

LOAD COMPENSATING DEVICE, IN PARTICULAR FOR LIFTING EQUIPMENT

DEVICE FOR VERIFYING THE DISCONNECTION OF THE CONTROL CLUSTERS OF A NUCLEAR REACTOR

L'INVENTION A POUR OBJET UN DISPOSITIF DE VERIFICATION DE LA CONNEXION DES TIGES DE COMMANDE DES GRAPPES DE CONTROLE AVANT ENLEVEMENT DES EQUIPEMENTS INTERNES D'UN REACTEUR NUCLEAIRE COMPORTANT, A L'INTERIEUR D'UNE FOSSE 10 FORMANT PISCINE, UNE CUVE 1 FERMEE PAR UN COUVERCLE AMOVIBLE ET CONTENANT LE COEUR ET UN ENSEMBLE DE GRAPPES DE CONTROLE MONTEES COULISSANTES DANS LES EQUIPEMENTS INTERNES SUPERIEURS FORMANT UNE STRUCTURE DE GUIDAGE AU-DESSUS DU COEUR, CHAQUE GRAPPE ETANT FIXEE SUR LA PARTIE INFERIEURE 32 D'UNE TIGE DE COMMANDE 3 SUSCEPTIBLE D'ETRE DETACHEE DE LA GRAPPE CORRESPONDANTE, APRES OUVERTURE DU COUVERCLE, AU MOYEN D'UN OUTIL DE DECONNEXION SUSPENDU A UNE MACHINE DE CHARGEMENT 2 DEPLACABLE AU-DESSUS DE LA PISCINE 10. LE DISPOSITIF DE VERIFICATION SELON L'INVENTION COMPREND UNE PERCHE 4 DE LONGUEUR SUPERIEURE A LA DISTANCE ENTRE LA PLATEFORME ET LE NIVEAU DES TETES DE TIGES DE COMMANDE, MUNIE A SA PARTIE SUPERIEURE DE MOYENS 44 DE SUSPENSION ET DE COMMANDE DE LA ROTATION DE LA PERCHE AUTOUR DE SON AXE VERTICAL ET A SA PARTIE INFERIEURE, D'UN MANCHON 5 DE CENTRAGE A UN NIVEAUDETERMINE SUR LA TETE DE LA TIGE DE COMMANDE 3 ET D'UN BRAS 7 S'ETENDANT TRANSVERSALEMENT A L'HORIZONTALE AU NIVEAU DES TETES 39 DES TIGES DECONNECTEES ET DE LONGUEURSUPERIEURE A LA DISTANCE ENTRE LES AXES DES GRAPPES. THE OBJECT OF THE INVENTION IS A DEVICE FOR VERIFYING THE CONNECTION OF THE CONTROL RODS OF THE CONTROL CLUSTERS BEFORE REMOVING THE INTERNAL EQUIPMENT OF A NUCLEAR REACTOR INCLUDING, INSIDE A PIT 10 FORMING A SWIMMING POOL, A TANK 1 CLOSED BY A REMOVABLE COVER CONTAINING THE HEART AND A SET OF SLIDING MOUNTED CONTROL CLUSTERS IN THE UPPER INTERNAL EQUIPMENT FORMING A GUIDING STRUCTURE ABOVE THE HEART, EACH CLUSTER IS ATTACHED TO THE LOWER PART 32 OF A 3 DIGITAL CONTROL STEM '' BE DETACHED FROM THE CORRESPONDING CLUSTER, AFTER OPENING THE COVER, BY MEANS OF A DISCONNECTION TOOL SUSPENDED FROM A LOADING MACHINE 2 ...

LOADING MACHINE FOR MOVING CLOSE NEARLY OBJECTS, ESPECIALLY FUEL ASSEMBLIES

In order to displace simultaneously two fuel elements (65, 66) in a reactor for example, or a plurality of similar members, a rolling trolley is fitted with a mast which includes a corresponding number of sections (71, 72) each comprising its own clamping and guiding means (73, 74) for the different fuel elements. One section at least is capable of horizontal displacement on the rolling trolley and rotates about its longitudinal axis. This system makes it possible to withdraw simultaneously two fuel elements from the core (64) and to place them in a modified position relative to each other on a storage structure (75) or in a working (inspection) locus.

Automatic gripper for handling loads

Handling device

Upper and lower internal equipments handling device for pressurized water nuclear reactor, has movable part moved between high utilization position, in which movable part protrudes above fixed part and retracted low position

The device (1) has a fixed part comprising four posts (15) vertically placed in a service position of the device, and a set of fixation devices (20) e.g. roto-lock type bayonet system, provided for fixing equipments. A movable part is moved between a high utilization position, in which the movable part protrudes above the fixed part and a retracted low position. The fixed part has a plate (2) arranged above the posts and integrated with the posts, and the movable part has a rod (21) parallel to the posts and slidingly mounted through a hole (23) formed in the plate.

RINGARD FOR TRANSFERRING NUCLEAR FUEL ASSEMBLIES AND NUCLEAR REACTOR COMPRISING SUCH A RINGARD

Grapple for nuclear reactor fuel cartridges

Patent FR2039528A5

DEVICE AND METHOD FOR GRIPPING AND HANDLING A FUEL ASSEMBLY IN INCLINED POSITION

Radioactive charge handling equipment

DEVICE FOR DESCENDING AND RUNNING NUCLEAR FUEL ELEMENTS IN PACKAGING ALVEOLES

L'installation comprend une caméra (9) suspendue à un pont roulant (6) en même temps qu'un palan (7) porteur de l'élément de combustible (8) à descendre ou monter. Elle indique la position du pont roulant (6) par rapport à l'alvéole (2) à occuper, et un mouvement déterminé du pont roulant (6) place l'élément de combustible (8) au-dessus de l'alvéole. Un avaloir (10) à l'entrée de l'alvéole (2), porteur d'une paire de caméras, effectue une seconde mesure de la position de l'élément de combustible (8) en même temps qu'un guidage.Application au chargement ou au déchargement d'éléments de combustible nucléaire dans des emballages de transport.

New automatic handling clamp

TRANSPORT SYSTEM

L'invention concerne un système de transport pour saisir et retenir, en toute sécurité, des objets. Selon l'invention, il a plusieurs loquets 3 qui saisissent un objet 11 à transporter par une rainure; pour le déplacement du loquet 3 est prévu un entraîneur 4 mobile dans un corps de base 1; deux pièces de préhension 2, 5 sont prévues, dont la première est fixée sur le corps de base 1 et dont la seconde est reliée pivotante à l'entraîneur 4; un crochet de grue peut saisir au choix l'une des deux pièces 2, 5 ou les deux ensemble et peut également pivoter la seconde 5. L'invention permet à un crochet de grue d'accomplir toutes ses fonctions, verrouillage, déverrouillage et transport. A transport system for safely grabbing and holding objects is disclosed. According to the invention, it has several latches 3 which grip an object 11 to be transported by a groove; for the movement of the latch 3 is provided a movable driver 4 in a base body 1; two gripping parts 2, 5 are provided, the first of which is fixed to the base body 1 and the second of which is pivotally connected to the driver 4; a crane hook can either grab one of the two parts 2, 5 or both together and can also pivot the second 5. The invention allows a crane hook to perform all of its functions, locking, unlocking and transport .

APPARATUS FOR INPUT AND MANIPULATION OF WORKPIECES FOR LASER WELDING SYSTEMS AND THE LIKE

LE DISPOSITIF DE MANUTENTION DE PIECES D'USINAGE SELON LA PRESENTE INVENTION EST DESTINE AU POSITIONNEMENT D'UNE PIECE D'USINAGE DANS UN POSTE DE SOUDURE A L'AIDE D'UN DISPOSITIF DE LEVAGE 15 POUR REDUIRE A UN MINIMUM LA CONTAMINATION DES SOUDURES. CE DISPOSITIF COMPREND UN DISPOSITIF DE SAISIE ET DE MANIPULATION 20 COMPRENANT UNE STRUCTURE DE TRAVERSE HORIZONTALE EXTENSIBLE TELESCOPIQUEMENT QUI PERMET DE DEPLACER UN MECANISME DE MACHOIRE CONCU POUR SAISIR ET POSITIONNER DE FACON REPEREE LA PIECE A SOUDER DANS LA CHAMBRE DE SOUDAGE 13. APPLICATIONS: ENTRE AUTRES, SOUDAGE DES ELEMENTS CONSTITUTIFS DES GRILLES DES ASSEMBLAGES COMBUSTIBLES NUCLEAIRES. THE WORKPIECE HANDLING DEVICE ACCORDING TO THE PRESENT INVENTION IS INTENDED FOR THE POSITIONING OF A WORKPIECE IN A WELDING STATION USING A LIFTING DEVICE 15 TO REDUCE CONTAMINATION OF THE WELDS TO A MINIMUM. THIS DEVICE INCLUDES A FEEDBACK AND HANDLING DEVICE 20 INCLUDING A TELESCOPIC EXTENSIBLE HORIZONTAL TRAVERSE STRUCTURE WHICH ALLOWS TO MOVE A JAW MECHANISM DESIGNED TO GRAB AND POSITION THE PIECAME APPLIED TO THE WELD 13 BETWEEN THE APPLICATION AND POSITION IN A MANNER. , WELDING OF THE CONSTITUTIVE ELEMENTS OF THE GRIDS OF NUCLEAR FUEL ASSEMBLIES.

Coupling Mechanism

Demountable structure for examination of nuclear fuel rods - assembled in deactivation pool, incorporating cells for fuel assemblies, automatically positioned extractor and examination station

Appts. for handling and examining fuel rods in the deactivation pool of a nuclear reactor incorporates a vertical tubular structure, an examination station, an extractor, carriages and winches and automatic position controllers. The structure can be taken to pieces and transported. In operation it stands on the bottom of the pool. It carries cells for housing the fuel assemblies and a stockage structure. The examination station is carried by the tubular structure. The extractor, for extracting, inserting and handling the rods, comprises a telescopic assembly of vertical tubes, tubes, the lowest one in the operating position carrying a claw with movable fingers operated by a cam to hold the rods. The carriages and winches are on rails on the upper part of the structure and enable the extractor to be moved in two horizontal directions at right angles to one another and in the vertical direction. Appts. allows the rods to be examined during the shutdown of the nuclear reactor without interference with the use of the power station. It can be used at different sites in the power station and is very safe in operation handling nuclear fuel.

Handling device for nuclear reactor

CHARGING MACHINE GRAPPLE OF A NUCLEAR REACTOR

L'invention concerne les réacteurs nucléaires. Le grappin de machine de rechargement faisant l'objet de l'invention est du type comportant un corps 3 dans lequel est placé un coulisseau 4 à l'une des extrémités duquel est articulé un organe actif 5 de préhension d'un assemblage combustible à manipuler 19 du réacteur nucléaire, et dont l'autre extrémité est liée mécaniquement à une tige 8 fixée au corps du grappin et déplacée par l'actionneur de la machine de rechargement, et est caractérisé en ce que ladite tige comporte une saillie sphérique 11 qui est engagée dans un alésage 12 ménagé dans le coulisseau 4 et qui se trouve en contact avec la surface de ce dernier, en formant ainsi une articulation principale 13 assurant la liaison mécanique entre le coulisseau 4 et la tige 8. L'invention permet notamment l'engagement sûr de la tête des assemblages combustibles dans l'organe actif du grappin même quand l'axe longitudinal de l'assemblage combustible ne coïncide pas avec l'axe longitudinal du grappin. The invention relates to nuclear reactors. The reloading machine grapple which is the subject of the invention is of the type comprising a body 3 in which is placed a slide 4 at one end of which is articulated an active member 5 for gripping a fuel assembly to be handled. 19 of the nuclear reactor, and the other end of which is mechanically linked to a rod 8 fixed to the body of the grapple and moved by the actuator of the reloading machine, and is characterized in that said rod comprises a spherical projection 11 which is engaged in a bore 12 formed in the slide 4 and which is in contact with the surface of the latter, thus forming a main articulation 13 providing the mechanical connection between the slide 4 and the rod 8. The invention allows in particular the safe engagement of the head of the fuel assemblies in the active member of the grapple even when the longitudinal axis of the fuel assembly does not coincide ...

DEVICE FOR DESCENDING AND RUNNING NUCLEAR FUEL ELEMENTS IN PACKAGING ALVEOLES

Nuclear reactor control rod handling gear

Three coaxial grabs are controlled independently and grasp respectively (starting with the innermost grab) a control rod extension sliding through the hollow head of the rod, the head of the rod, and a guide tube surrounding the rod between the upper wall of the reactor protection vessel and a seating for the rod in the core. The inner grab is pref. fixed to the end of a control cable passing through an axial channel in the body of the middle grab.

Nuclear reactor refueling methods and apparatuses

TOOL FOR HANDLING A CLUSTER OF CONSUMABLE POISONOUS PENCILS.

Cet outil, comportant une tête de préhension (1) de la grappe (2), reliée à un organe de manutention (3) coulissant dans un corps d'outil (4) entre une position active dans laquelle la tête (1) et au moins une partie de l'organe (3) font saillie hors du corps (4) et une position escamotée dans laquelle la tête (1), l'organe de manutention (3) et au moins une partie de la grappe (2) s'étendent dans le corps, et des peignes (5, 6, 7, 8, 9, 10) de guidage des crayons, à une extrémité du corps (4) et déplaçables entre une position escamotée dans laquelle ils s'étendent le long du corps (4) et une position active dans laquelle ils s'étendent perpendiculairement à celui-ci, pour guider les crayons, est caractérisé en ce qu'il comporte des moyens (13) de sollicitation des peignes en position active, et des moyens d'escamotage (15) de ces peignes, déplaçables entre une position d'escamotage des peignes et une position de libération de ceux-ci, par la tête (1) et/ou l'organe de manutention (3) lors de leur déplacement entre leurs positions active et escamotée dans le corps (4). This tool, comprising a gripping head (1) of the cluster (2), connected to a handling member (3) sliding in a tool body (4) between an active position in which the head (1) and the at least a part of the member (3) protrudes out of the body (4) and a retracted position in which the head (1), the handling member (3) and at least a part of the cluster (2) s 'extend in the body, and combs (5, 6, 7, 8, 9, 10) for guiding the rods, at one end of the body (4) and movable between a retracted position in which they extend along the body (4) and an active position in which they extend perpendicularly thereto, to guide the rods, is characterized in that it comprises means (13) for biasing the combs in the active position, and means for 'retraction (15) of these combs, movable between a position of retraction of the combs and a position of release thereof, by the ...

RINGARD FOR TRANSFERRING NUCLEAR FUEL ASSEMBLIES AND NUCLEAR REACTOR COMPRISING SUCH A RINGARD

Pour permettre le transfert d'assemblages de combustible nucléaire irradiés au-dessus d'un liquide de refroidissement dans lequel baignent normalement ces assemblages, tout en assurant leur refroidissement, il est proposé un ringard 10 comportant un tube guide 12 formé de deux parois coaxiales 12a, 12b entre lesquelles circule de bas en haut le liquide prélevé à la partie inférieure du tube guide par une pompe 38 ou un système équivalent. Le liquide de refroidissement s'écoule ensuite par gravité dans l'assemblage 16 suspendu en grappin 14 logé dans le tube guide. Un tel ringard, utilisé dans un réacteur nucléaire à neutrons rapides, réduit de façon sensible la hauteur de la cuve du réacteur et, par conséquent, le coût de ce dernier. To allow the transfer of irradiated nuclear fuel assemblies above a cooling liquid in which these assemblies normally bathe, while ensuring their cooling, a corny 10 is proposed comprising a guide tube 12 formed of two coaxial walls 12a. , 12b between which circulates from bottom to top the liquid withdrawn from the lower part of the guide tube by a pump 38 or an equivalent system. The coolant then flows by gravity into the suspended grapple assembly 16 14 housed in the guide tube. Such old-fashioned use in a fast neutron nuclear reactor significantly reduces the height of the reactor vessel and, consequently, the cost of the latter.

GRAPPLE FOR THE FUEL ASSEMBLIES OF A NUCLEAR REACTOR

L'INVENTION CONCERNE LA TECHNIQUE NUCLEAIRE. LE GRAPPIN FAISANT L'OBJET DE L'INVENTION EST CARACTERISE NOTAMMENT EN CE QU'IL EST EQUIPE D'UN FOURREAU15 MONTE SUR SON CORPS3 DE FACON QU'IL PUISSE SE DEPLACER PAR RAPPORT A CE DERNIER, UNE TRANCHE DE CE FOURREAU COOPERANT AVEC UN RESSORT16 PLACE SUR LEDIT CORPS, SON AUTRE TRANCHE PORTANT UN EMBOUT17 DONT LA FORME CORRESPOND A CELLE D'UNE SURFACE DE CONTACT PREVUE SUR LA TETE9 DE L'ASSEMBLAGE COMBUSTIBLE10, LA LONGUEUR DUDIT FOURREAU ETANT CHOISIE DE MANIERE QUE LORSQUE LA TETE9 DE L'ASSEMBLAGE COMBUSTIBLE10 EST SAISIE PAR LES GRIFFES14 DU GRAPPIN, LA TRANCHE DE L'EMBOUT17 S'APPLIQUE SUR LADITE SURFACE DE CONTACT DE LA TETE DE L'ASSEMBLAGE COMBUSTIBLE SOUS L'ACTION DUDIT RESSORT. L'INVENTION S'APPLIQUE NOTAMMENT AUX REACTEURS NUCLEAIRES DONT LES ASSEMBLAGES COMBUSTIBLES UTILISES DONNENT LIEU A DES DEGAGEMENTS DE CHALEUR RESIDUELS IMPORTANTS. THE INVENTION CONCERNS NUCLEAR TECHNOLOGY. THE GRAPPLE WHICH IS THE OBJECT OF THE INVENTION IS CHARACTERIZED IN PARTICULAR IN THAT IT IS EQUIPPED WITH A HOLDALL15 MOUNTED ON ITS BODY3 SO THAT IT CAN MOVE IN RELATION TO THE LATTER, A SLICE OF THIS HOLDER COOPERATING WITH A SPRING16 PLACED ON ITS BODY, ITS OTHER SLICE CARRYING A TIP17 THE SHAPE OF WHICH CORRESPONDS TO THAT OF A CONTACT SURFACE PROVIDED ON THE HEAD9 OF THE FUEL ASSEMBLY10, THE LENGTH OF THE SAID SHELF BEING CHOSEN AS WHEN THE ASSEMBLY9 OF THE HEAD9 FUEL10 IS GRABBED BY THE CLAWS14 OF THE GRAPPLE, THE SLICE OF THE NOZZLE 17 APPLIES TO THE SAID CONTACT SURFACE OF THE HEAD OF THE FUEL ASSEMBLY UNDER THE ACTION OF THE SAID SPRING. THE INVENTION APPLIES IN PARTICULAR TO NUCLEAR REACTORS WHOSE FUEL ASSEMBLIES USED GIVE PLACE TO SIGNIFICANT RESIDUAL HEAT RELEASES.

Patent FR2395571B1

DEVICE AND METHOD FOR HANGING A STEERING ROD FOR A CONTROL CLUSTER IN A NUCLEAR REACTOR

LE DISPOSITIF D'ACCROCHAGE COMPORTE, POUR CHAQUE TIGE DE MANOEUVRE22: UNE EMBASE28 FIXEE A LA PARTIE HAUTE DE LA STRUCTURE INTERNE ET COAXIALE A UN TUBE GUIDE; PLUSIEURS CLIQUETS34 REPARTIS AUTOUR DE L'AXE DE L'EMBASE ET MONTES DE FACON A POUVOIR BASCULER AUTOUR D'UN AXE HORIZONTAL VERS UNE POSITION D'ENGAGEMENT AVEC UNE PORTION, MUNIE DE GORGES OU DE CANNELURES CIRCONFERENCIELLES, DE LA TIGE CONTENUE DANS LE TUBE ET A PARTIR DE CETTE POSITION; UN COULISSEAU MOBILE AXIALEMENT SUR L'EMBASE VERS UNE POSITION HAUTE OU IL PROVOQUE L'ENGAGEMENT DES CLIQUETS DANS UNE GORGE DE LA TIGE ET A PARTIR DE CETTE POSITION; ET DES MOYENS ELASTIQUES PRENANT APPUI SUR L'EMBASE ET TENDANT A ENGAGER LES CLIQUETS DE LA TIGE. LE COULISSEAU EST DIMENSIONNE DE FACON A ETRE MAINTENU PAR LE FOURREAU CORRESPONDANT A UN EMPLACEMENT SUFFISAMMENT ELOIGNE DE LA POSITION BASSE POUR QUE LES CLIQUETS SOIENT DEGAGES, QUELLE QUE SOIT LA TEMPERATURE QUI REGNE DANS LE REACTEUR. THE HANGING DEVICE INCLUDES, FOR EACH MANEUVERING ROD22: A BASE28 FIXED AT THE TOP OF THE INTERNAL STRUCTURE AND COAXIAL TO A GUIDE TUBE; SEVERAL RATCHETS34 DISTRIBUTED AROUND THE AXLE OF THE BASE AND MOUNTS IN A WAY TO BE ABLE TO SWITCH AROUND A HORIZONTAL AXIS TOWARDS A COMMITMENT POSITION WITH A PORTION, PROVIDED WITH GORGES OR CIRCUMFERENTIAL GROOVES, OF THE ROD CONTAINED IN THE TUBE AND FROM THIS POSITION; A MOBILE SLIDER AXIALALLY ON THE BASE TOWARDS A HIGH POSITION WHERE IT CAUSES THE ENGAGEMENT OF THE RATCHETS IN A THROAT OF THE ROD AND FROM THIS POSITION; AND ELASTIC MEANS USING THE BASE AND TENDING TO ENGAGE THE RATCHET RATCHETS. THE SLIDER IS DIMENSIONED TO BE HELD BY THE SLEEVE CORRESPONDING TO A LOCATION SUFFICIENTLY AWAY FROM THE LOW POSITION SO THAT THE PICKERS ARE CLEAR, WHAT IS THE TEMPERATURE IN THE REACTOR.

HANDLING DEVICE FOR FUEL ASSEMBLY AND HANDLING ASSEMBLY COMPRISING SUCH A DEVICE

Un objet de l'invention est un dispositif de manutention pour assemblage combustible nucléaire comprenant : - un corps ; - des moyens de préhension aptes à coopérer avec un assemblage combustible de manière à saisir ou à libérer ledit assemblage ; - des moyens de commande des moyens de préhension aptes à commander lesdits moyens de préhension entre une position de saisie et une position de libération dudit assemblage, et inversement ; - des moyens d'aspiration aptes à générer une aspiration d'un gaz de refroidissement à travers le dispositif de manutention et à travers l'assemblage lorsqu'il est saisi par ledit dispositif. Un autre objet de l'invention est un ensemble de manutention pour assemblage combustible nucléaire, comprenant : - un dispositif de manutention, - un support de réception apte à réceptionner un assemblage combustible et apte à coopérer avec le dispositif de manutention. An object of the invention is a handling device for nuclear fuel assembly comprising: - a body; - gripping means able to cooperate with a fuel assembly so as to grasp or release said assembly; - control means for gripping means able to control said gripping means between a gripping position and a release position of said assembly, and vice versa; - Suction means capable of generating a suction of a cooling gas through the handling device and through the assembly when it is gripped by said device. Another object of the invention is a handling assembly for nuclear fuel assembly, comprising: - a handling device, - a receiving support capable of receiving a fuel assembly and capable of cooperating with the handling device.

Examination apparatus for examining nuclear fuel rod of underwater nuclear reactor, has optical reflection device comprising optical reflection element for reflecting light rays and directing reflected light rays to image pickup device

The apparatus (6) has an image pickup device (16) comprising an optical input (20) with an entrance optical axis (AA). Another image pickup device (22) comprises a sensor (30) and an optical lens (28) that is provided with an optical image pickup axis (BB). An optical reflection device (24) is arranged between the input and the latter image pickup device and comprises a single optical reflection element (32) for reflecting light rays entering the input and directing the reflected light rays to the latter image pickup device. The former image pickup device comprises a water-tight compartment. The water-tight compartment is filled with water or a mixture of water and alcohol, and the image pickup devices are designed as cameras or standard cameras. The optical reflection element is designed as a prism or a mirror. The sensor is designed as a complementary metal-oxide-semiconductor (CMOS) sensor.

DEVICE FOR HANDLING CONSTITUENT ELEMENTS OF THE HEART OF A REACTOR

DANS CE DISPOSITIF, LE MECANISME D'ENTRAINEMENT D'UNE BARRE DE COMMANDE COMPORTE DES ORGANES DE PREHENSION 87 PORTANT DES CROCHETS RENTRANTS ET SAILLANTS ENGRENANT AVEC UNE TETE DE MANIPULATION DE LA BARRE DE COMMANDE ET AVEC UNE TETE DE MANIPULATION DE CHAQUE ELEMENT CONSTITUTIF DU COEUR DU REACTEUR, UNE TETE DE MANOEUVRE 92 OUVRANT ET FERMANT LES ORGANES DE PREHENSION, UN MECANISME D'ENTRAINEMENT 71, 73 DEPLACANT LONGITUDINALEMENT LA TETE 92, UN SUPPORT DE LEVAGE 65 SUPPORTANT LEDIT MECANISME DE LEVAGE ET LES ORGANES DE PREHENSION, UN MECANISME DE LEVAGE 60, 61, 62 ENTRAINANT LONGITUDINALEMENT LE SUPPORT 65, UN SUPPORT DE LEVAGE 54 SUPPORTANT LE MECANISME DE LEVAGE 60, 61, 62 ET LE SUPPORT 65, UN MECANISME DE LEVAGE 50, 51, 52 ENTRAINANT LONGITUDINALEMENT LE SUPPORT DE LEVAGE 54 ET UN SUPPORT 40 RACCORDANT LE DERNIER MECANISME A BOUCHON ROTATIF DU COEUR DU REACTEUR. APPLICATION NOTAMMENT AUX REACTEURS SURREGENERATEURS RAPIDES. IN THIS DEVICE, THE DRIVING MECHANISM OF A CONTROL BAR INCLUDES HOLDERS 87 BEARING RETURNING AND PROJECTING HOOKS ENGAGING WITH A HANDLING HEAD OF THE CONTROL BAR AND WITH A HANDLING HEAD OF EACH COMPONENT ELEMENT OF THE HEART OF THE REACTOR, AN OPERATING HEAD 92 OPENING AND CLOSING THE GRIPPERS, A DRIVING MECHANISM 71, 73 MOVING THE HEAD 92 LONGITUDINALLY, A LIFTING BRACKET 65 SUPPORTING ITS LIFTING MECHANISM AND THE LIFT MECHANISM, A 60, 61, 62 LONGITUDINALLY DRIVING THE SUPPORT 65, A LIFTING SUPPORT 54 SUPPORTING THE LIFTING MECHANISM 60, 61, 62 AND THE SUPPORT 65, A LIFTING MECHANISM 50, 51, 52 LONGITUDINALLY DRIVING THE LIFTING SUPPORT 54 AND A SUPPORT 40 CONNECTING THE LAST REACTOR CORE ROTARY PLUG MECHANISM. APPLICATION ESPECIALLY TO FAST SUPERREGENERATOR REACTORS.

Patent FR2137015B2

Lifting system for use e.g. in nuclear reactor

The lifting system, for use e.g. in a hostile environment such as a nuclear PWR core pool, consists of a motor and reduction gear unit (1) with a horizontal winch drum (2), and flexible elements (3,4) which pass round pulleys (12,13) connected to a load (16) to be raised.

DEVICE FOR EXTRACTING FROM THE ACTIVE ZONE OF A NUCLEAR REACTOR THE FUEL ASSEMBLIES AND THE COVERS OF THE CONTROL AND PROTECTION SYSTEMS

L'invention concerne la technique nucléaire. Le dispositif faisant l'objet de l'invention est caractérisé en ce que l'alésage de la barre creuse 6 a un diamètre qui lui permet de s'engager sur l'élément à extraire 4, et qu'à celle des extrémités de la barre 6 qui est orientée vers l'élément à extraire 4, est monté un grappin supplémentaire 10 destiné à coopérer avec la surface extérieure de l'élément à extraire 4, ladite barre ayant une longueur suffisante pour que le grappin supplémentaire 10 atteigne l'extrémité de l'élément à extraire 4 opposée à la tête de celui-ci, quand le grappin principal 7 est engagé sur ladite tête. L'invention s'applique notamment aux réacteurs à neutrons rapides, refroidi par métal liquide. The invention relates to nuclear technology. The device forming the subject of the invention is characterized in that the bore of the hollow bar 6 has a diameter which allows it to engage on the element to be extracted 4, and that of the ends of the bar 6 which is oriented towards the element to be extracted 4, is mounted an additional grapple 10 intended to cooperate with the outer surface of the element to be extracted 4, said bar having a sufficient length for the additional grapple 10 to reach the end of the element to be extracted 4 opposite the head thereof, when the main gripper 7 is engaged on said head. The invention applies in particular to fast neutron reactors, cooled by liquid metal.