A robotic arm for handling fuel in a nuclear reactor is provided, the robotic arm comprising a movement mechanism for moving the robotic arm along an x-axis. The movement mechanism can be coupled to an arm portion whose centre line is parallel with the x-axis, a grab head portion which is pivotally mounted to the arm portion. The grab head can be rotated vertically to be parallel to a z-axis, and have a telescopic portion that allows the grab head to extend along the z-axis and a grip mechanism at its distal end for gripping fuel assemblies of the nuclear reactor.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
B25J 13/08 - Commandes pour manipulateurs au moyens de dispositifs sensibles, p. ex. à la vue ou au toucher
G21C 19/105 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande à éléments de couplage effectuant un mouvement de serrage ou d'extension
A depressurisation valve (100) for a pressurised cooling circuit, comprising a main valve (101), a pilot line (104) fluidically coupled to the inlet (110) and closable by a first control valve (105), the first control valve controlled by pressure at the inlet to open above a low pressure threshold, a valve dome (106) containing a first piston (107) coupled to the main valve, the valve dome being fluidically coupled to the pilot line, wherein in normal operation, pressure on the first piston urges the valve into the closed position, and when the pressure in the coolant circuit is lower than the low pressure threshold, the first control valve closes to allow the main valve to open, when the pressure in the coolant circuit is higher than the high pressure threshold, the second control valve is configured to open and reduce the pressure in the valve dome.
F16K 31/40 - Moyens de fonctionnementDispositifs de retour à la position de repos actionnés par un fluide et dans lesquels il y a alimentation constante du moteur à fluide par le fluide provenant de la canalisation avec un organe actionné électriquement dans la décharge du moteur
A depressurisation valve (100) for a pressurised cooling circuit, comprising a main valve (101), a pilot line (104) fluidically coupled to the inlet (110) and closable by a first control valve (105), the first control valve controlled by pressure at the inlet to open above a low pressure threshold, a valve dome (106) containing a first piston (107) coupled to the main valve, the valve dome being fluidically coupled to the pilot line, wherein in normal operation, pressure on the first piston urges the main valve into the closed position, and when the pressure in the coolant circuit is lower than the low pressure threshold, the first control valve closes to allow the main valve to open, when the pressure in the coolant circuit is higher than the high pressure threshold, a second control valve opens to transmit fluid pressure to apply a second force to the main valve opposing the first force to urge the main valve to the open position.
Disclosed is a method of tensioning/detensioning closure studs of a nuclear reactor vessel. The closure studs are spaced about a circumference of the reactor vessel so as to attach an integrated head package (IHP) of the reactor vessel to a body of the reactor vessel. The method comprises supporting a first stud tensioner device on a trolley, moving the trolley across a movement surface from a stored position to a deployment position adjacent the reactor vessel, engaging the first stud tensioner device with one or more of the closure studs, and operating the first stud tensioner device to tension/detension the one or more closure studs.
B23P 19/06 - Machines pour mettre ou retirer les vis ou les écrous
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
G21C 13/073 - Obturateurs pour enceintes de réacteurs, p. ex. rotatifs
G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
A lift head for a reactor pressure vessel comprising a lift head which can be coupled and removed to a reactor pressure vessel head, and radiation shielding. The radiation shielding is connectable to the lift head such that the lift head and the radiation shield encase the reactor pressure vessel head and any head package contents removed from a reactor pressure vessel with the reactor pressure vessel head. The radiation shield may be of a clam shell construction. The lift head may be provided with a mechanism for fastening and unfastening the bolts connecting the reactor pressure vessel head to the reactor pressure vessel. The lift head may be provided with monitoring equipment to monitor the core internals.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 11/00 - Blindage structurellement associé avec le réacteur
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
A nuclear plant steam generator is provided. The steam generator has an upright elongate body and has tension members extending from proximal ends attaching to respective attachment positions on the elongate body to distal ends which are configured to attach to respective load-supporting attachment positions in the nuclear plant. Each proximal end is lower than its respective distal end. In use, the tension members are loaded in tension by the steam generator to transmit substantially all of the weight of the steam generator to the load-supporting attachment positions in the nuclear plant.
A fixture is provided for mounting a closure head of a nuclear reactor pressure vessel during manufacture of the closure head. The closure head has a central section for penetration therethrough by control rod guide tubes and a peripheral section containing a circumferential row of through holes corresponding to positions of bolt holes by which, in use, the closure head is bolted to the reactor pressure vessel. The fixture has a support ring providing a circumferential row of upstanding projections which are matingly engageable through respective holes of the circumferential row of holes of the peripheral section of the closure head to mount the closure head on the support ring. The fixture further has an underframe for holding the support ring and closure head mounted thereon off the ground.
G21C 13/073 - Obturateurs pour enceintes de réacteurs, p. ex. rotatifs
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
The present disclosure provides an integrated head package for a nuclear power generation system, the integrated head package comprising a closure head, and a control rod drive mechanism housed within a shroud. The control rod drive mechanism comprises at least one drive rod extending through the closure head and having a coupling element for releasably coupling to a control rod assembly within a reactor core. The at least one drive rod is movable to a maintenance/refuelling position in which the at least one drive rod is uncoupled from the control rod assembly and at least partially retracted into the integrated head package. The integrated head package further comprises at least one engagement feature for securing the at least one drive rod in the maintenance/refuelling position.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
G21C 13/073 - Obturateurs pour enceintes de réacteurs, p. ex. rotatifs
There is described a method of manufacturing a dome (2), the method comprising: providing a plurality of beams (6, 106, 206, 306), each of the plurality of beams (6, 106, 206, 306) comprising one or more slots (16, 22); and engaging at least one of the slots (16, 22) of each of the plurality of beams (6, 106, 206, 306) with a slot (16, 22) of the one or more slots (16, 22) of another of the plurality of beams (6, 106, 206, 306) so as to form at least part of the dome (2). There is also described a dome (2) manufactured in accordance with the method.
Disclosed is a nuclear power generation system comprising a reactor vessel comprising a body defining a cavity housing a reactor core, and an integrated head package having a closure head for closing an opening to the cavity. The system also comprises a containment structure having a working floor surrounding and substantially vertically aligned with the opening to the cavity.
G21C 13/073 - Obturateurs pour enceintes de réacteurs, p. ex. rotatifs
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
The present disclosure provides a lifting and transport device for lifting upper internals from a reactor core of a nuclear power generation system in a deployment location and transporting them to a storage location. The lifting/transport device comprises a device body formed of radioactive shielding material, the device body defining a storage chamber having an open base. The device further comprises a movable sealing plate formed of radioactive shielding material, the sealing plate being movable between an open position in which the storage chamber is open and a closed position in which the storage chamber is sealed. There is also a lifting system mounted within the storage chamber having a lifting rig for releasable connection to the upper internals and configured to raise the upper internals to within the storage chamber when the device is in the deployment location and the plate is in the open position. The device comprises wheels for guiding movement of the lifting/transport device between the deployment location and the storage location.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
12.
A METHOD OF MANUFACTURING A DOME MADE OF WELDED COMPONENTS
Method of manufacturing a dome comprising: providing a plurality of components; joining a first and a second component together, joining the first and second components together comprising: positioning the first component and the second component in an initial position in which the first surfaces of components are angled from each other by a first angle; melting a volume of material extending between the first and the second component, the volume of material increasing in thickness from the second surfaces to the first surfaces; and the volume of material cooling and solidifying so as to join the first component and the second component together, the cooling of the volume of material reducing the angle between the first surfaces to a second angle less than the first angle such that the first surfaces face towards a centre of the dome and the first and second components form part of the dome.
B23K 33/00 - Extrémités de pièces spécialement profilées pour effectuer des assemblages brasés ou soudésRemplissage des joints continus ainsi formés
B23K 31/02 - Procédés relevant de la présente sous-classe, spécialement adaptés à des objets ou des buts particuliers, mais non couverts par un seul des groupes principaux relatifs au brasage ou au soudage
There is disclosed a vessel connection (220) for a metallic pressure vessel comprising: a wall portion (221) configured to form a portion of a vessel wall; a pipe extension (222) integrally formed with the wall portion; and a channel (223) through the wall and the pipe extension. There is also disclosed a method of designing a canister for forming a vessel connection.
The present disclosure provides a lifting device for lifting a closure head assembly from a reactor vessel body in a nuclear power generation system. The lifting device comprises at least one lifting element having an engagement surface configured to engage an underside surface of the closure head assembly. The at least one lifting element is axially adjustable in height between a retracted position in which its axial height is such that the closure head assembly seals against the body of the reactor vessel and an extended position in which its axial height is such that the closure head assembly is raised above the body of the reactor vessel.
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
A nuclear reactor is provided. The reactor including: plural fuel rods containing fissile material; plural control rods, each made of a first neutron-absorbing material, the control rods being inserted between the fuel rods to reduce the rate of a fission reaction of the fissile material and put the reactor in a shutdown state, but being operable to move in and out of the reactor to vary the rate of the fission reaction when the reactor is critical and generating useful power; and plural refuelling and/or storage rods, each made of a second neutron-absorbing material different to the first material, the refuelling and/or storage rods being inserted between the fuel rods to further reduce the rate of the fission reaction and maintain the shutdown state.
G21C 19/40 - Dispositions pour prévenir l'apparition de conditions critiques, p. ex. pendant le stockage
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
A nuclear power plant has a nuclear reactor including a reactor pressure vessel which houses plural fuel rods containing fissile material. The nuclear power plant further has means for submerging the reactor pressure vessel in water and thereby water-cooling the reactor pressure vessel in the event of an emergency requiring cooling of the nuclear reactor. The nuclear power plant further has a primary core catcher outwardly of the reactor pressure vessel, the primary core catcher being formed of a material suitable for retaining molten corium in the event corium escapes the reactor pressure vessel The nuclear power plant further has secondary core catcher outwardly of the primary core catcher, the secondary core catcher lining a tank which is water-filled in normal use of the plant to submerge and thereby water-cool the primary core catcher. The secondary core catcher is also is formed of a material suitable for retaining molten corium in the event corium escapes the primary core catcher.
A nuclear reactor is provided. The reactor includes a reactor pressure vessel housing plural fuel rods containing fissile material, the reactor pressure vessel having an upper, removable, vessel head. The reactor further includes control rods, each made of a neutron-absorbing material. The control rods are inserted into the reactor through the vessel head and between the fuel rods to control the rate of the fuel rods' fission reaction. The control rods are movable over a normal range of insertion positions relative to the vessel head to control the power output of the reactor when it is critical and generating useful power, and to put the reactor in a sub-critical shutdown state. The reactor further includes control rod drive mechanisms carried by the vessel head and operable to drive the movements of the control rods. The control rod drive mechanisms are controllable to release the control rods when a vessel opening operation is performed in which the reactor is in the shutdown state and the vessel head is lifted upwards from the reactor pressure vessel such that the control rods slide therethrough to remain stationary relative to the fuel rods to maintain the shutdown state. The reactor further has monitoring unit to identify whether a control rod is accidently lifting with the vessel head.
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
07 - Machines et machines-outils
11 - Appareils de contrôle de l'environnement
35 - Publicité; Affaires commerciales
37 - Services de construction; extraction minière; installation et réparation
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
41 - Éducation, divertissements, activités sportives et culturelles
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Chemical substances, chemical materials and chemical
preparations, all for use in science and industry; chemicals
for use in industry and science; fuel for nuclear reactors;
fuel elements for nuclear reactors; graphites for nuclear
energy; fissionable material for nuclear energy; catalysts
for chemical processes; moderating materials for nuclear
reactors; chemical preparations and compositions for use in
the construction and civil engineering industries. Power-operated tools; machines for handling nuclear fuels;
uninterruptible power supplies (machines) for the generation
of electrical energy; power supply apparatus [generators];
and parts and fittings for the aforesaid. Apparatus and installations for heating; nuclear
installations; modular nuclear installations and reactors;
nuclear generators; nuclear reactors; nuclear power plant
installations; installations for processing nuclear fuel and
nuclear moderating material; apparatus for desalination;
apparatus for synthetic fuel and hydrogen production; and
parts and fittings for the aforesaid. Procurement services; procurement of contracts concerning
energy supply; management, business information, and
business consulting services in the field of nuclear energy,
nuclear power plants, and modular nuclear installations and
reactors; management, business information, and business
consulting services in relation to the design, licensing,
operation, maintenance, and decommissioning of nuclear power
plants and modular nuclear installations and reactors;
promoting the adoption of nuclear power; promoting the use
of synthetic fuels and hydrogen generated using nuclear
power; promoting the use of nuclear power for water
desalination; and consultancy, information, and advisory
services in relation to all the aforesaid. Construction, installation, and repair services;
construction, installation, servicing, renovation, repair,
and maintenance of nuclear installations, nuclear
generators, nuclear reactors, nuclear power plant
installations, modular nuclear installations, and modular
nuclear reactors; construction, installation, servicing,
renovation, repair, and maintenance of installations for
processing nuclear fuel and nuclear moderating material;
construction, installation, servicing, renovation, repair,
and maintenance of energy production plants and machines;
construction, installation, servicing, renovation, repair,
and maintenance of power generating apparatus and
installations; construction management services; industrial
cleaning services for nuclear installations, nuclear plants,
and nuclear facilities; hazardous waste clean-up services;
demolition and decommissioning services for nuclear
installations, nuclear plants, and nuclear facilities;
machinery installation; and consultancy, information, and
advisory services in relation to all the aforesaid. Treatment of materials; recycling of waste and trash;
production and generation of energy; production and
generation of energy by nuclear power plants; hazardous
waste treatment and management services; industrial toxic
waste disposal; nuclear waste treatment; decontamination of
nuclear waste and nuclear plants; nuclear fuel reprocessing;
nuclear fuel recycling; conversion of nuclear fuels; rental
of generators; rental of equipment for energy production and
generation; processing and refinement of fuel materials;
desalination of water; and consultancy, information, and
advisory services in relation to all the aforesaid. Education, instruction, and training services; education,
instruction, and training services in the field of energy
production and generation, nuclear power, and nuclear power
plants; arranging and conducting of seminars and
conferences; and consultancy, information, and advisory
services in relation to all the aforesaid. Scientific and technological services and research and
design relating thereto; industrial analysis, industrial
research and industrial design services; design of nuclear
installations, nuclear power plants, modular nuclear
installations, and modular nuclear reactors; design of
equipment and parts and fittings for nuclear installations,
nuclear power plants, modular nuclear installations, and
modular nuclear reactors; scientific, technical and
technological information and consultancy services in the
field of nuclear energy, energy production and generation,
and modular nuclear installations and reactors; analysis and
research in the field of nuclear energy, energy production
and generation, and modular nuclear installations and
reactors; architectural services relating to the development
and construction of nuclear installations, nuclear power
plants, modular nuclear installations, and modular nuclear
reactors; nuclear engineering services; testing of nuclear
material; scientific, technical and technological
information, consultancy, and advisory services connected
with the use of nuclear power; scientific, technical and
technological information, consultancy, and advisory
services connected with the use of nuclear power for
synthetic fuel and hydrogen production; scientific,
technical and technological information, consultancy, and
advisory services connected with the use of nuclear power
for water desalination; and consultancy, scientific,
technical and technological information, and advisory
services in relation to all the aforesaid.
A reactor control system for a nuclear reactor, the reactor control system comprising: one or more hollow tubes comprising neutron absorbing material, each having a first end and a second end; a pump connected to the first end of each hollow tube and operable to control the amount of a first fluid within the hollow tube, the first fluid comprising a neutron moderator, wherein: the pump is controlled based on a level of reactivity in the nuclear reactor, and the second end of the hollow tubes is in fluid communication with a second fluid, the second fluid having a neutron moderating capacity lower than 10% of that of the first fluid.
G21C 7/06 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion
G21C 7/26 - Commande de la réaction nucléaire par déplacement du modérateur ou de parties de celui-ci
G21C 9/033 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p. ex. fusible pour réacteur par un fluide absorbant
A depressurisation valve (100) for a pressurised cooling circuit, comprising a main valve (101), a pilot line (104) fluid ica lly coupled to the inlet (110) and closable by a first control valve (105), the first control valve controlled by pressure at the inlet to open above a low pressure threshold, a valve dome (106) containing a first piston (107) coupled to the main valve, the valve dome being fluid ica lly coupled to the pilot line, wherein in normal operation, pressure on the first piston urges the valve into the closed position, and when the pressure in the coolant circuit is lower than the low pressure threshold, the first control valve closes to allow the main valve to open, when the pressure in the coolant circuit is higher than the high pressure threshold, the second control valve is configured to open and reduce the pressure in the valve dome.
A depressurisation valve (100) for a pressurised cooling circuit, comprising a main valve (101), a pilot line (104) fluidically coupled to the inlet (110) and closable by a first control valve (105), the first control valve controlled by pressure at the inlet to open above a low pressure threshold, a valve dome (106) containing a first piston (107) coupled to the main valve, the valve dome being fluidically coupled to the pilot line, wherein in normal operation, pressure on the first piston urges the main valve into the closed position, and when the pressure in the coolant circuit is lower than the low pressure threshold, the first control valve closes to allow the main valve to open, when the pressure in the coolant circuit is higher than the high pressure threshold, a second control valve opens to transmit fluid pressure to apply a second force to the main valve opposing the first force to urge the main valve to the open position.
There is disclosed a containment system for a nuclear plant, the containment system comprising a pressure vessel defining a containment space for containing nuclear plant structures, a working floor extending from within the containment space to outside the pressure vessel, an access opening in the pressure vessel for providing access from the working floor outside the pressure vessel to the working floor in the containment space, and an access door provided within the pressure vessel. The access door is configured to slidably move downwardly with respect to the pressure vessel from a closed position in which it closes the access opening to seal the pressure vessel, and an open position in which it reveals the access opening and is received in a door space in the working floor. The access door comprises a first integral floor plug which is configured to plug the door space in the working floor when the access door is in the open position, to provide a substantially continuous working floor surface from outside the pressure vessel to within the containment space.
G21C 13/028 - Joints, p. ex. pour les cuves de pression ou les enceintes de confinement
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21F 7/005 - Passages blindés à travers les paroisVerrouillagesDispositifs de transfert entre chambres
A depressurisation valve for a cooling system including a main chamber having a main valve, a pilot line having a secondary valve and a blowdown line; the main valve being located to seal a path of the coolant system of the nuclear reactor. The main chamber is connected to the cooling circuit via the pilot line allowing coolant to enter the main chamber, and the blowdown line allows coolant to escape from the main chamber, the pilot line having a lower fluid resistance than the blowdown line. The pressure of coolant in the main chamber maintains the main valve in a closed position, and under elevated temperature and/or pressure conditions fluid is prevented from entering the main chamber via a closure of the secondary valve on the pilot line and reduce the pressure from the valve, moving it to its open position.
F16K 17/04 - Soupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage ouvrant sur excès de pression d'un côtéSoupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage fermant sur insuffisance de pression d'un côté actionnés par ressort
F16K 31/06 - Moyens de fonctionnementDispositifs de retour à la position de repos électriquesMoyens de fonctionnementDispositifs de retour à la position de repos magnétiques utilisant un aimant
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
07 - Machines et machines-outils
11 - Appareils de contrôle de l'environnement
35 - Publicité; Affaires commerciales
37 - Services de construction; extraction minière; installation et réparation
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
41 - Éducation, divertissements, activités sportives et culturelles
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
(1) Chemical substances, chemical materials and chemical preparations, all for use in science and industry; chemicals for use in industry and science; fuel for nuclear reactors; fuel elements for nuclear reactors; graphites for nuclear energy; fissionable material for nuclear energy; catalysts for chemical processes; moderating materials for nuclear reactors; chemical preparations and compositions for use in the construction and civil engineering industries.
(2) Power-operated tools; machines for handling nuclear fuels; uninterruptible power supplies (machines) for the generation of electrical energy; power supply apparatus [generators]; and parts and fittings for the aforesaid.
(3) Apparatus and installations for heating; nuclear installations; modular nuclear installations and reactors; nuclear generators; nuclear reactors; nuclear power plant installations; installations for processing nuclear fuel and nuclear moderating material; apparatus for desalination; apparatus for synthetic fuel and hydrogen production; and parts and fittings for the aforesaid. (1) Procurement services; procurement of contracts concerning energy supply; management, business information, and business consulting services in the field of nuclear energy, nuclear power plants, and modular nuclear installations and reactors; management, business information, and business consulting services in relation to the design, licensing, operation, maintenance, and decommissioning of nuclear power plants and modular nuclear installations and reactors; promoting the adoption of nuclear power; promoting the use of synthetic fuels and hydrogen generated using nuclear power; promoting the use of nuclear power for water desalination; and consultancy, information, and advisory services in relation to all the aforesaid.
(2) Construction, installation, and repair services; construction, installation, servicing, renovation, repair, and maintenance of nuclear installations, nuclear generators, nuclear reactors, nuclear power plant installations, modular nuclear installations, and modular nuclear reactors; construction, installation, servicing, renovation, repair, and maintenance of installations for processing nuclear fuel and nuclear moderating material; construction, installation, servicing, renovation, repair, and maintenance of energy production plants and machines; construction, installation, servicing, renovation, repair, and maintenance of power generating apparatus and installations; construction management services; industrial cleaning services for nuclear installations, nuclear plants, and nuclear facilities; hazardous waste clean-up services; demolition and decommissioning services for nuclear installations, nuclear plants, and nuclear facilities; machinery installation; and consultancy, information, and advisory services in relation to all the aforesaid.
(3) Treatment of materials; recycling of waste and trash; production and generation of energy; production and generation of energy by nuclear power plants; hazardous waste treatment and management services; industrial toxic waste disposal; nuclear waste treatment; decontamination of nuclear waste and nuclear plants; nuclear fuel reprocessing; nuclear fuel recycling; conversion of nuclear fuels; rental of generators; rental of equipment for energy production and generation; processing and refinement of fuel materials; desalination of water; and consultancy, information, and advisory services in relation to all the aforesaid.
(4) Education, instruction, and training services; education, instruction, and training services in the field of energy production and generation, nuclear power, and nuclear power plants; arranging and conducting of seminars and conferences; and consultancy, information, and advisory services in relation to all the aforesaid.
(5) Scientific and technological services and research and design relating thereto; industrial analysis, industrial research and industrial design services; design of nuclear installations, nuclear power plants, modular nuclear installations, and modular nuclear reactors; design of equipment and parts and fittings for nuclear installations, nuclear power plants, modular nuclear installations, and modular nuclear reactors; scientific, technical and technological information and consultancy services in the field of nuclear energy, energy production and generation, and modular nuclear installations and reactors; analysis and research in the field of nuclear energy, energy production and generation, and modular nuclear installations and reactors; architectural services relating to the development and construction of nuclear installations, nuclear power plants, modular nuclear installations, and modular nuclear reactors; nuclear engineering services; testing of nuclear material; scientific, technical and technological information, consultancy, and advisory services connected with the use of nuclear power; scientific, technical and technological information, consultancy, and advisory services connected with the use of nuclear power for synthetic fuel and hydrogen production; scientific, technical and technological information, consultancy, and advisory services connected with the use of nuclear power for water desalination; and consultancy, scientific, technical and technological information, and advisory services in relation to all the aforesaid.
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
01 - Produits chimiques destinés à l'industrie, aux sciences ainsi qu'à l'agriculture
07 - Machines et machines-outils
11 - Appareils de contrôle de l'environnement
35 - Publicité; Affaires commerciales
37 - Services de construction; extraction minière; installation et réparation
41 - Éducation, divertissements, activités sportives et culturelles
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Treatment of materials by means of exposure to ionising radiation; recycling of waste and trash; production and generation of energy; production and generation of energy by nuclear power plants; hazardous waste treatment services; industrial toxic waste treatment services; nuclear waste treatment; decontamination of nuclear waste and nuclear plants; nuclear fuel reprocessing; nuclear fuel recycling; conversion of nuclear fuels in the nature of reprocessing of nuclear fuels; rental of electricity generators; rental of equipment for energy production and generation; processing and refinement of fuel materials; desalination of water; and consultancy, information, and advisory services in relation to all the aforesaid Chemical substances, chemical materials and chemical preparations, all for use in science and industry; chemicals for use in industry and science; fuel for nuclear reactors; fuel elements being fuel for nuclear reactors; manufactured and synthetic graphites for nuclear energy; fissionable material for nuclear energy namely uranium; catalysts for chemical processes; moderating materials for nuclear reactors, namely water for industrial purposes, heavy water, sodium, carbon dioxide for industrial purposes and manufactured and synthetic graphite; chemical preparations and compositions for use in the construction and civil engineering industries Machines for handling nuclear fuels; uninterruptible power supplies, namely, auxiliary power supply machines for the generation of electrical energy; power supply apparatus, namely, electricity generators; and structural and replacement parts and fittings for the aforesaid Nuclear generators; nuclear reactors; nuclear power plant installations; installations for processing nuclear fuel and nuclear moderating material; apparatus for desalination; and structural or replacement parts and fittings for the aforesaid Procurement services namely, procurement of contracts for others for the purchase of nuclear power plant installations; procurement of contracts concerning energy supply namely, procurement of contracts for others for the purchase of energy; business management, business information, and business consulting services in the field of nuclear energy, nuclear power plants, and modular nuclear installations and reactors; business management, business information, and business consulting services in relation to the design, licensing, operation, maintenance, and decommissioning of nuclear power plants and modular nuclear installations and reactors; promoting the adoption of nuclear power for others; promoting the use of synthetic fuels and hydrogen generated using nuclear power for others; promoting the use of nuclear power for water desalination for others; and consultancy, information, and advisory services in relation to all the aforesaid Construction, installation, servicing, renovation, repair, and maintenance of nuclear installations, nuclear generators, nuclear reactors, nuclear power plant installations, modular nuclear installations, and modular nuclear reactors; construction, installation, servicing, renovation, repair, and maintenance of installations for processing nuclear fuel and nuclear moderating material; construction, installation, servicing, renovation, repair, and maintenance of energy production plants and machines; construction, installation, servicing, renovation, repair, and maintenance of power generating apparatus and installations; construction management services; industrial cleaning services for nuclear installations, nuclear plants, and nuclear facilities; hazardous waste clean-up services; demolition and decommissioning services for nuclear installations, nuclear plants, and nuclear facilities; machinery installation; and consultancy, information, and advisory services in relation to all the aforesaid Education, instruction, and training services, namely, conducting classes, seminars, conferences, workshops, field trips in the field of energy production and generation, nuclear power, and nuclear power plants; arranging and conducting of seminars and conferences in the field of energy production and generation, nuclear power, and nuclear power plants; and consultancy, information, and advisory services in relation to all the aforesaid Industrial design services; design of nuclear installations, nuclear power plants, modular nuclear installations, and modular nuclear reactors; design of equipment and parts and fittings for nuclear installations, nuclear power plants, modular nuclear installations, and modular nuclear reactors; technical and technological information and consultancy services in the field of nuclear energy, energy production and generation, and modular nuclear installations and reactors; scientific and technological services, namely, analysis and scientific research in the field of nuclear energy, energy production and generation, and modular nuclear installations and reactors; architectural services relating to the development and construction of nuclear installations, nuclear power plants, modular nuclear installations, and modular nuclear reactors; nuclear engineering services; testing of nuclear material; scientific, technical and technological information, consultancy, and advisory services connected with the use of nuclear power; scientific, technical and technological information, consultancy, and advisory services connected with the use of nuclear power for synthetic fuel and hydrogen production; scientific, technical and technological information, consultancy, and advisory services connected with the use of nuclear power for water desalination; and consultancy, scientific, technical and technological information, and advisory services in relation to all the aforesaid
A lift head for a reactor pressure vessel comprising a lift head which can be coupled and removed to a reactor pressure vessel head, and radiation shielding. The radiation shielding is connectable to the lift head such that the lift head and the radiation shield encase the reactor pressure vessel head and any head package contents removed from a reactor pressure vessel with the reactor pressure vessel head. The radiation shield may be of a clam shell construction. The lift head may be provided with a mechanism for fastening and unfastening the bolts connecting the reactor pressure vessel head to the reactor pressure vessel. The lift head may be provided with monitoring equipment to monitor the core internals.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
A robotic arm for handling fuel in a nuclear reactor is provided, the robotic arm comprising a movement mechanism for moving the robotic arm along an x-axis. The movement mechanism can be coupled to an arm portion whose centre line is parallel with the x-axis, a grab head portion which is pivotally mounted to the arm portion. The grab head can be rotated vertically to be parallel to a z-axis, and have a telescopic portion that allows the grab head to extend along the z-axis and a grip mechanism at its distal end for gripping fuel assemblies of the nuclear reactor.
G21C 19/105 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande à éléments de couplage effectuant un mouvement de serrage ou d'extension
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
28.
PRESSURE-CONTAINING SILO FOR A PRESSURISED WATER REACTOR NUCLEAR POWER PLANT
A pressure-containing silo for one or more components on a primary coolant circuit of a nuclear reactor having nuclear fuel assemblies cooled by coolant circulating the primary coolant circuit, the silo defining a release space which, in a loss-of-coolant accident releasing the pressurised coolant water from the one or more components therein, receives and contains the released water and steam, at increasing pressure, formed therefrom; wherein the silo is formed from plural, substantially identical, stacked and joined modular units, each having: a concrete body, a metal liner which lines a surface of the concrete body, and which, when the units are stacked and joined, is sealed edge-to-edge with metal liners of neighbouring units forming an inward-facing, pressure-containing skin surrounding the release space, and plural conduits which, when the units are stacked, align with the conduits of neighbouring units to receive elongate tensioning members for post-stressing the concrete of the bodies.
The present disclosure provides a lifting and transport device for lifting upper internals from a reactor core of a nuclear power generation system in a deployment location and transporting them to a storage location. The lifting/transport device comprises a device body formed of radioactive shielding material, the device body defining a storage chamber having an open base. The device further comprises a movable sealing plate formed of radioactive shielding material, the sealing plate being movable between an open position in which the storage chamber is open and a closed position in which the storage chamber is sealed. There is also a lifting system mounted within the storage chamber having a lifting rig for releasable connection to the upper internals and configured to raise the upper internals to within the storage chamber when the device is in the deployment location and the plate is in the open position. The device comprises wheels for guiding movement of the lifting/transport device between the deployment location and the storage location.
G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
The present disclosure provides an integrated head package for a nuclear power generation system, the integrated head package comprising a closure head, and a control rod drive mechanism housed within a shroud. The control rod drive mechanism comprises at least one drive rod extending through the closure head and having a coupling element for releasably coupling to a control rod assembly within a reactor core. The at least one drive rod is movable to a maintenance/refuelling position in which the at least one drive rod is uncoupled from the control rod assembly and at least partially retracted into the integrated head package. The integrated head package further comprises at least one engagement feature for securing the at least one drive rod in the maintenance/refuelling position.
G21C 13/073 - Obturateurs pour enceintes de réacteurs, p. ex. rotatifs
G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
Disclosed is a nuclear power generation system comprising a reactor vessel comprising a body defining a cavity housing a reactor core, and an integrated head package having a closure head for closing an opening to the cavity. The system also comprises a containment structure having a working floor surrounding and substantially vertically aligned with the opening to the cavity.
Disclosed is a method of tensioning/detensioning closure studs of a nuclear reactor vessel. The closure studs are spaced about a circumference of the reactor vessel so as to attach an integrated head package (IHP) of the reactor vessel to a body of the reactor vessel. The method comprises supporting a first stud tensioner device on a trolley, moving the trolley across a movement surface from a stored position to a deployment position adjacent the reactor vessel, engaging the first stud tensioner device with one or more of the closure studs, and operating the first stud tensioner device to tension/detension the one or more closure studs.
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 13/073 - Obturateurs pour enceintes de réacteurs, p. ex. rotatifs
B25B 29/02 - Dispositifs pour appliquer une tension prédéterminée à un boulon
B23P 19/06 - Machines pour mettre ou retirer les vis ou les écrous
33.
NUCLEAR REACTOR AND METHOD OF OPENING A NUCLEAR REACTOR
A nuclear reactor is provided. The reactor includes a reactor pressure vessel housing plural fuel rods containing fissile material, the reactor pressure vessel having an upper, removable, vessel head. The reactor further includes control rods, each made of a neutron-absorbing material. The control rods are inserted into the reactor through the vessel head and between the fuel rods to control the rate of the fuel rods' fission reaction. The control rods are movable over a normal range of insertion positions relative to the vessel head to control the power output of the reactor when it is critical and generating useful power, and to put the reactor in a sub-critical shutdown state. The reactor further includes control rod drive mechanisms carried by the vessel head and operable to drive the movements of the control rods. The control rod drive mechanisms are controllable to release the control rods when a vessel opening operation is performed in which the reactor is in the shutdown state and the vessel head is lifted upwards from the reactor pressure vessel such that the control rods slide therethrough to remain stationary relative to the fuel rods to maintain the shutdown state. The reactor further has monitoring unit to identify whether a control rod is accidently lifting with the vessel head.
G21C 7/08 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion par déplacement des éléments de commande solides, p. ex. barres de commandes
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
The present disclosure provides a refuelling device for lifting a fuel rod assembly from a reactor core of a nuclear power generation system in a deployment location and transporting it to a storage location. The refuelling device comprises a device body having an open base and defining a chamber for housing a coolant. A sealing plate is movable between an open position in which the chamber is open and a closed position in which the chamber is sealed. The device further comprises a shielding element formed of radioactive shielding material and moveably mounted within the chamber. It has a storage cavity having an open lower end, the shielding element being movable between a retracted position in which it is fully contained within the chamber and an extended position in which it extends from the chamber through the open base of the device body. The device further comprises a rod lifting system having a rod connector for releasable connection to the fuel rod assembly and configured to raise the fuel rod assembly to within the storage cavity when the device is in the deployment location, the sealing plate is in the open position and the shielding element is in its extended position.
G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
The present disclosure provides a lifting device for lifting a closure head assembly from a reactor vessel body in a nuclear power generation system. The lifting device comprises at least one lifting element having an engagement surface configured to engage an underside surface of the closure head assembly. The at least one lifting element is axially adjustable in height between a retracted position in which its axial height is such that the closure head assembly seals against the body of the reactor vessel and an extended position in which its axial height is such that the closure head assembly is raised above the body of the reactor vessel.
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
A nuclear reactor is provided. The reactor including: plural fuel rods containing fissile material; plural control rods, each made of a first neutron-absorbing material, the control rods being inserted between the fuel rods to reduce the rate of a fission reaction of the fissile material and put the reactor in a shutdown state, but being operable to move in and out of the reactor to vary the rate of the fission reaction when the reactor is critical and generating useful power; and plural refuelling and/or storage rods, each made of a second neutron- absorbing material different to the first material, the refuelling and/or storage rods being inserted between the fuel rods to further reduce the rate of the fission reaction and maintain the shutdown state.
A nuclear power plant has a nuclear reactor including a reactor pressure vessel which houses plural fuel rods containing fissile material. The nuclear power plant further has means for submerging the reactor pressure vessel in water and thereby water-cooling the reactor pressure vessel in the event of an emergency requiring cooling of the nuclear reactor. The nuclear power plant further has a primary core catcher outwardly of the reactor pressure vessel, the primary core catcher being formed of a material suitable for retaining molten corium in the event corium escapes the reactor pressure vessel. The nuclear power plant further has secondary core catcher outwardly of the primary core catcher, the secondary core catcher lining a tank which is water-filled in normal use of the plant to submerge and thereby water-cool the primary core catcher. The secondary core catcher is also is formed of a material suitable for retaining molten corium in the event corium escapes the primary core catcher.
G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
G21C 15/12 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p. ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles provenant de l'enceinte sous pressionAménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p. ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles provenant de l'enceinte d'enveloppe
There is disclosed a containment system for a nuclear plant, the containment system comprising a pressure vessel defining a containment space for containing nuclear plant structures, a working floor extending from within the containment space to outside the pressure vessel, an access opening in the pressure vessel for providing access from the working floor outside the pressure vessel to the working floor in the containment space, and an access door provided within the pressure vessel. The access door is configured to slidably move downwardly with respect to the pressure vessel from a closed position in which it closes the access opening to seal the pressure vessel, and an open position in which it reveals the access opening and is received in a door space in the working floor. The access door comprises a first integral floor plug which is configured to plug the door space in the working floor when the access door is in the open position, to provide a substantially continuous working floor surface from outside the pressure vessel to within the containment space.
Cladding of the interior of a component part of a pressure vessel is shown. A lining which conforms to at least a portion of the interior geometry of the component is positioned in the interior of the component. The lining is then pressed into the component past its yield strength. The lining is then fused to the component.
F17C 1/10 - Récipients sous pression, p. ex. bouteilles de gaz, réservoirs de gaz, cartouches échangeables avec des moyens pour assurer une protection contre la corrosion, p. ex. due à un acide à l'état gazeux
C21D 9/08 - Traitement thermique, p. ex. recuit, durcissement, trempe ou revenu, adapté à des objets particuliersFours à cet effet pour corps tubulaires ou tuyaux
C22F 1/10 - Modification de la structure physique des métaux ou alliages non ferreux par traitement thermique ou par travail à chaud ou à froid du nickel ou du cobalt ou de leurs alliages
40.
A PRESSURE-CONTAINING SILO FOR A PRESSURISED WATER REACTOR NUCLEAR POWER PLANT
A pressure-containing silo for one or more components on a primary coolant circuit of a nuclear reactor is provided. The pressure-containing silo for one or more components on a primary coolant circuit of a nuclear reactor having nuclear fuel assemblies which are cooled by coolant circulating around the primary coolant circuit, the silo defining a release space which, in the event of a loss-of-coolant accident releasing the pressurised coolant water from the one or more components contained therein, receives and contains the released water and steam, at increasing pressure, formed therefrom; wherein the silo is formed from plural, substantially identical, stacked and joined modular units, each modular unit having: a concrete body, a metal liner which lines a surface of the concrete body, and which, when the units are stacked and joined, is sealed edge-to-edge with the metal liners of neighbouring units to form an inward-facing, pressure-containing skin surrounding the release space, and plural conduits which, when the units are stacked, align with the conduits of neighbouring units to receive elongate tensioning members for post-stressing the concrete of the bodies.
A nuclear power plant having a protective superstructure including a first end region configured to cover a nuclear reactor in a containment structure, a second end region opposite the first end region and configured to cover a cooling water pump house, and a central region between the first and second end regions and configured to cover a turbine hall. The superstructure has an oval-shaped plan profile, the oval having a greater degree of curvature at the first end region than at the second end region.
E04H 5/02 - Bâtiments ou groupes de bâtiments à des fins industrielles, p. ex. pour centrales énergétiques ou usines
E04H 9/14 - Bâtiments, groupes de bâtiments ou abris conçus pour résister à des situations extérieures anormales, p. ex. à des bombardements, à des séismes ou à des climats extrêmes, ou pour se protéger de ces situations contre d'autres influences dangereuses, p. ex. tornades, crues
A depressurisation valve for a cooling system comprising: a main chamber having a main valve, a pilot line having a secondary valve and a blowdown line; the main valve being located to seal a path of the coolant system of the nuclear reactor. The main chamber is connected to the cooling circuit via the pilot line allowing coolant to enter the main chamber, and the blowdown line allows coolant to escape from the main chamber, the pilot line having a lower fluid resistance than the blowdown line. The pressure of coolant in the main chamber maintains the main valve in a closed position, and under elevated temperature and/or pressure conditions fluid is prevented from entering the main chamber via a closure of the secondary valve on the pilot line and reduce the pressure from the valve, moving it to its open position.
F16K 17/04 - Soupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage ouvrant sur excès de pression d'un côtéSoupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage fermant sur insuffisance de pression d'un côté actionnés par ressort
F16K 31/06 - Moyens de fonctionnementDispositifs de retour à la position de repos électriquesMoyens de fonctionnementDispositifs de retour à la position de repos magnétiques utilisant un aimant
A depressurisation valve for a cooling system comprising: a main chamber having a main valve, a pilot line having a secondary valve and a blowdown line; the main valve being located to seal a path of the coolant system of the nuclear reactor. The main chamber is connected to the cooling circuit via the pilot line allowing coolant to enter the main chamber, and the blowdown line allows coolant to escape from the main chamber, the pilot line having a lower fluid resistance than the blowdown line. The pressure of coolant in the main chamber maintains the main valve in a closed position, and under elevated temperature and/or pressure conditions fluid is prevented from entering the main chamber via a closure of the secondary valve on the pilot line and reduce the pressure from the valve, moving it to its open position.
F16K 17/00 - Soupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage
F16K 17/38 - Soupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage fonctionnant sous l'action de circonstances extérieures, p. ex. un choc, un changement de position d'une température excessive
F16K 31/383 - Moyens de fonctionnementDispositifs de retour à la position de repos actionnés par un fluide et dans lesquels il y a alimentation constante du moteur à fluide par le fluide provenant de la canalisation le fluide travaillant directement sur les deux côtés du moteur à fluide, un des côtés étant relié par un étranglement et le moteur étant actionné par la décharge effectuée de ce même côté le fluide agissant sur un piston
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
A nuclear power plant (10) comprises a nuclear reactor (12), the nuclear reactor comprising reactor fuel elements (14), a reactor vessel (16) surrounding the nuclear reactor (12) and a primary shield (18) surrounding the reactor vessel (16). The reactor fuel elements (14) are arranged between a first height (H1) and a second height (H2) above the first height (H1). The primary shield (18) comprises a base portion (30), an intermediate portion (32) and a top portion (34). The base portion (30) has an upper height (H3) below the first height (H1) and the base portion (30) comprises concrete. The top portion (34) has a lower height (H4) above the second height (H2) and the top portion (34) comprises concrete. The intermediate portion (32) is arranged vertically between the base portion (30) and the top portion (34) of the primary shield (18). The intermediate portion (32) comprises at least one support structure (36, 36A, 36B, 36C) and a matrix material containing tungsten or boron (32A, 32B), and the least one support structure (36, 36A, 36B, 36C) extends between the top portion (34) and the bottom portion (30) of the primary shield (18).
G21C 1/08 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p. ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
Apparatus for moving one or more processing devices relative to an object to be processed, comprising: first and second mounting units configured to be secured in a fixed position relative to the object to be processed and between which one or more tension members are mounted under tension; one or more carriages respectively connected to the one or more tension members, each of the carriages configured to accommodate a respective processing device; and a drive unit configured to move the one or more tension members so as to move the one or more carriages relative to the object.
A method and apparatus for applying a cladding layer to a surface of a component uses a cladding tool having a maximum reach less than the size of the surface. Geometry of the surface is segmented into a plurality of tessellated segments, each of which has a peripheral extent determined by a maximum reach of the cladding tool. A nominal tool subpath for each tessellated segment is generated, and then combined to generate a nominal tool path for depositing the cladding layer on the surface. The surface is clad using the nominal toolpath, including a process of adjusting the nominal tool path to an adjusted tool path that accounts for dimensions of the bead to be deposited by the tool to match an edge of the bead to be deposited with an edge of a previously deposited bead.
B23K 9/16 - Soudage ou découpage à l'arc utilisant des gaz de protection
B23K 9/167 - Soudage ou découpage à l'arc utilisant des gaz de protection et une électrode non consommable
B23K 9/23 - Soudage ou découpage à l'arc tenant compte des propriétés des matériaux à souder
B23K 37/02 - Chariots pour supporter l'outillage pour souder ou découper
B23K 37/04 - Dispositifs ou procédés auxiliaires non spécialement adaptés à un procédé couvert par un seul des autres groupes principaux de la présente sous-classe pour maintenir ou mettre en position les pièces
F17C 1/10 - Récipients sous pression, p. ex. bouteilles de gaz, réservoirs de gaz, cartouches échangeables avec des moyens pour assurer une protection contre la corrosion, p. ex. due à un acide à l'état gazeux
B23K 26/03 - Observation, p. ex. surveillance de la pièce à travailler
B33Y 50/02 - Acquisition ou traitement de données pour la fabrication additive pour la commande ou la régulation de procédés de fabrication additive
B23K 103/18 - Matériaux comportant des matières différentes
A coolant injection system for a nuclear power generation system includes the coolant injection system, and method of operation of the coolant injection system. The nuclear power generation system includes a reactor pressure vessel having a reactor core, a pressuriser in fluid communication with the reactor pressure vessel, and the injection system, which comprises a make-up tank having a tank inlet and a tank outlet. The injection system has an operating condition, and a fault response condition, and is configured to switch between these conditions when coolant level in the pressuriser drops below a threshold level. In the operating condition, the tank outlet is isolated from the reactor pressure vessel such that coolant is retained in the make-up tank, and the tank inlet is in fluid communication with the reactor pressure vessel and the pressuriser.
The nuclear power generation system of the present invention comprises a reactor vessel. It further comprises a first crane gantry defining a fuel rod path along which nuclear fuel rods can be moved to/from the reactor vessel and a second crane gantry defining a component path along which reactor vessel components can be moved to/from the reactor vessel. The the first and second crane gantries both have a fixed radial orientation relative to the reactor vessel.
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
B66C 17/06 - Ponts roulants à chariot transbordeur comportant une ou plusieurs poutres principales sensiblement horizontales dont les extrémités reposent directement sur des roues ou des rouleaux se déplaçant sur une voie soutenue par des supports espacés spécialement adaptés à des buts particuliers, p. ex. dans des fonderies ou des forgesPonts roulants à chariot transbordeur comportant une ou plusieurs poutres principales sensiblement horizontales dont les extrémités reposent directement sur des roues ou des rouleaux se déplaçant sur une voie soutenue par des supports espacés combinés avec des appareils auxiliaires servant des buts particuliers
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
B66C 19/00 - Ponts roulants ou portiques fixes ou mobiles, portant un chariot ou un treuil mobile
There is disclosed a nuclear power plant (10), comprising a reactor pressure vessel (11); a steam generator (16) arranged to generate steam utilising thermal energy generated within the reactor pressure vessel (11); and a fluid circuit (14) for transferring thermal energy from the reactor pressure vessel to the steam generator. The plant also comprises a coolant reservoir (29) for storing coolant for supply to the steam generator under gravity in emergency conditions. The steam generator (16) comprises a steam drying zone (26) comprising one or more steam separators (28) configured to dry steam; and the steam generator and coolant reservoir are configured such that when coolant is supplied from the coolant reservoir to the steam generator in emergency conditions the coolant stays below a threshold level (32) defined by the steam drying zone.
Cladding of the interior of a component part of a pressure vessel is shown. A lining which conforms to at least a portion of the interior geometry of the component is positioned (303) in the interior of the component. The lining is then pressed (304) into the component past its yield strength. The lining is then fused (305) to the component.
F17C 1/10 - Récipients sous pression, p. ex. bouteilles de gaz, réservoirs de gaz, cartouches échangeables avec des moyens pour assurer une protection contre la corrosion, p. ex. due à un acide à l'état gazeux
A method of heat treating a localised region of a component including providing a heat treatment assembly with two or more subassemblies. Each subassembly is configured to partially circumscribe a portion of the component for heat treatment. Each subassembly includes a housing configured to partially circumscribe a portion of the component. An insulator and a heater are provided within the housing and extend to partially circumscribe a component and are arranged such that the insulator is between a wall of the housing and the heater. The method includes positioning the subassemblies adjacently around the component so that the subassemblies fully circumscribe the component. The subassemblies are connected together. The method includes activating the heater to heat the component in a region adjacent the heater.
C21D 9/50 - Traitement thermique, p. ex. recuit, durcissement, trempe ou revenu, adapté à des objets particuliersFours à cet effet pour joints de soudure
C21D 9/00 - Traitement thermique, p. ex. recuit, durcissement, trempe ou revenu, adapté à des objets particuliersFours à cet effet
H05B 3/14 - Éléments chauffants caractérisés par la composition ou la nature des matériaux ou par la disposition du conducteur caractérisés par la composition ou la nature du matériau conducteur le matériau étant non métallique
H05B 3/28 - Éléments chauffants ayant une surface s'étendant essentiellement dans deux dimensions, p. ex. plaques chauffantes non flexibles le conducteur chauffant enrobé dans un matériau isolant
A method of constructing a nuclear reactor module includes providing formwork defining a chamber in which is mounted a nuclear reactor comprising a nuclear reactor pressure vessel configured to contain nuclear fuel when in use, the formwork being housed within a containment structure configured to contain an internal pressure generated by an escape of coolant from a reactor coolant circuit. The method further includes filling one or more voids within the formwork with concrete through at least one concrete supply pipe that extends from outside of the containment structure, through the containment structure, and to the formwork; and venting the one or more voids within the formwork through one or more vent pipes, thereby forming a concrete support structure for the nuclear reactor.
A spray nozzle 10 for a laser deposition apparatus comprises an array of nozzle apertures 16 arranged side-by-side, and a powder supply chamber 18 in fluid communication with the nozzle apertures 16. In use the powder supply chamber 18 supplies powder to the nozzle apertures 16 under pressure so as to cause a wide powder stream to be discharged from the array of nozzle apertures 16. When used with a laser deposition apparatus 100, a relatively wide coating of a uniform thickness can be deposited.
B05B 5/00 - Pulvérisation électrostatiqueDispositifs de pulvérisation comportant des moyens pour charger électriquement le pulvérisatPulvérisation de liquides ou d'autres matériaux fluides par voies électriques
B23K 26/00 - Travail par rayon laser, p. ex. soudage, découpage ou perçage
B05D 1/30 - Procédés pour appliquer des liquides ou d'autres matériaux fluides aux surfaces par gravité uniquement
B23K 26/14 - Travail par rayon laser, p. ex. soudage, découpage ou perçage en utilisant un écoulement de fluide, p. ex. un jet de gaz, associé au faisceau laserBuses à cet effet
B23K 26/34 - Soudage au laser pour des finalités autres que l’assemblage