A nuclear reactor comprises a pressure vessel containing a nuclear reactor core. A reactor core cooling system comprises a standpipe including a plurality of orifices in fluid communication with a refueling water storage tank (RWST) to drain water from the RWST into the standpipe, and an injection line configured to drain water from the standpipe to the pressure vessel. In some embodiments the standpipe is disposed in the RWST, while in other embodiments the standpipe is disposed outside of the RWST and cross-connection pipes connect the plurality of orifices with the RWST. The reactor core cooling system may further comprise a valve configured to control flow through one orifice of the plurality of orifices in fluid communication with the RWST based on water level in the standpipe. The valve may comprise a float valve having its float disposed in the standpipe.
A nuclear reactor comprises a pressure vessel containing a nuclear reactor core. A reactor core cooling system comprises a standpipe including a plurality of orifices in fluid communication with a refueling water storage tank (RWST) to drain water from the RWST into the standpipe, and an injection line configured to drain water from the standpipe to the pressure vessel. In some embodiments the standpipe is disposed in the RWST, while in other embodiments the standpipe is disposed outside of the RWST and cross-connection pipes connect the plurality of orifices with the RWST. The reactor core cooling system may further comprise a valve configured to control flow through one orifice of the plurality of orifices in fluid communication with the RWST based on water level in the standpipe. The valve may comprise a float valve having its float disposed in the standpipe.
In a pressurized water reactor (PWR), emergency core cooling (ECC) responds to depressurization due to a vessel penetration break at the top of the pressure vessel by draining water from a body of water through an injection line into the pressure vessel. A barrier operates concurrently with the ECC to suppress flow of liquid water from the pressure vessel out the vessel penetration break. The barrier may comprise one or more of: (1) an injection line extension passing through the central riser to drain water into the central riser; (2) openings in a lower portion of a central riser to shunt some upward flow from the central riser into a lower portion of the downcomer annulus; and (3) a surge line providing fluid communication between a pressurizer volume at the top of the pressure vessel and the remainder of the pressure vessel which directs water outboard toward the downcomer annulus.
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 15/26 - Cyclage du fluide réfrigérant par convection, p. ex. utilisant des cheminées, utilisant des canaux divergents
A spacer grid welding fixture comprises a frame sized to receive an assembled spacer grid comprising a first set of parallel straps and a second set of parallel straps oriented orthogonally to the first set of parallel straps, the first and second sets of parallel straps interlocked together by slots cut into the straps. A first set of grid engagement bars is placed on a first side of the spacer grid with each grid engagement bar arranged parallel with the straps of the first set of parallel straps and engaging the straps of the second set of parallel straps. A second set of grid engagement bars is placed on an opposite second side of the spacer grid with each grid engagement bar arranged parallel with the straps of the second set of parallel straps and engaging the straps of the first set of parallel straps.
B23K 37/00 - Dispositifs ou procédés auxiliaires non spécialement adaptés à un procédé couvert par un seul des autres groupes principaux de la présente sous-classe
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
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 1/09 - Dispositions pour la régulation de pression, c.-à-d. pressuriseurs
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
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
F04D 13/10 - Ensembles comprenant les pompes et leurs moyens d'entraînement la pompe étant entraînée par l'électricité pour utilisation en position immergée adaptés pour l'utilisation dans les forages de mine
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
An apparatus including a lower end fitting having a top planar surface, a bottom planar surface, a counterbore defined therebetween, an opening extending from the counterbore to the top planar surface, and a lock recess that extends both radially outwardly from the counterbore and extends inwardly into the lower end fitting from the bottom planar surface. The apparatus includes a guide tube having a lower end and an end plug configured to connect with the lower end of the guide tube. The end plug has a threaded shaft sized to pass through the opening of the lower end fitting, and a female lock nut has a deformable side wall configured to be swaged into the recess of the lower end fitting. The lock recess remains visible as viewed from the bottom planar surface of the lower end fitting when the female lock nut is fully disposed in the counterbore.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
F16B 39/02 - Blocage des vis, boulons ou écrous dans lequel le verrouillage s'effectue après vissage
B25B 23/00 - Parties constitutives ou accessoires des clés à écrous, clés anglaises, tournevis
F16B 23/00 - Têtes de boulons ou de vis de forme spéciale pour permettre leur rotation à l'aide d'un outil
A nuclear reactor has a core installed on a lower core plate and formed from multiple fuel assemblies, each fuel assembly including a structural cage assembly. The structural cage assembly has an upper end fitting, mid grids, and a lower end fitting (LEF). The LEF positions the fuel assembly using four locating pins located at each corner of the LEF. The pins position the fuel assembly laterally by mating with receiving holes in the lower core plate. The locating pins have a chamfered tip with a flat end. The chamfered tip allows for a greater positioning margin when installing the fuel assembly in the core by guiding the pins into holes in the lower core plate, and the flat tip provides strength and stability in case the assembly is inadvertently rested on the tip of the pin instead of the LEF pads.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 3/12 - Moyens formant partie de l'élément pour le positionner dans le cœur du réacteurEntretoises extérieures à cet effet
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant des éléments combustibles de différentes compositionsFaisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p. ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 5/06 - Moyens pour placer ou pour supporter les éléments combustibles
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
A nuclear reactor comprises a nuclear reactor core disposed in a pressure vessel. An isolation valve protects a penetration through the pressure vessel. The isolation valve comprises: a mounting flange connecting with a mating flange of the pressure vessel; a valve seat formed into the mounting flange; and a valve member movable between an open position and a closed position sealing against the valve seat. The valve member is disposed inside the mounting flange or inside the mating flange of the pressure vessel. A biasing member operatively connects to the valve member to bias the valve member towards the open position. The bias keeps the valve member in the open position except when a differential fluid pressure across the isolation valve and directed outward from the pressure vessel exceeds a threshold pressure.
A power distribution plate (PDP) sits on top of a support plate. Control rod drive mechanism (CRDM) units are mounted on top of the PDP, but the PDP is incapable of supporting the weight of the CRDM units and instead transfers the load to a support plate. The PDP has receptacles which receive cable modules each including mineral insulated (MI) cables, the MI cables being connected with the CRDM units. The PDP may further include a set of hydraulic lines underlying the cable modules and connected with the CRDM units. The cable modules in their receptacles define conduits or raceways for their MI cables and for any underlying hydraulic lines.
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
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 13/00 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
G21C 17/116 - Passages ou isolateurs, p. ex. pour câbles électriques
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 7/16 - Aménagements de conduite hydrauliques ou pneumatiques
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
11.
Resistance pressure weld for nuclear reactor fuel rod tube end plug
A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.
An apparatus and method for system safety analysis evaluation is provided, the apparatus including processing circuitry configured for generating a calculation matrix for a system, generating a plurality of models based on the calculation matrix, performing a benchmarking or convolution analysis of the plurality of models, identifying a design envelope based on the benchmarking or convolution analysis, deriving uncertainty models from the benchmarking or convolution analysis, deriving an assessment judgment based on the uncertainty models and acceptance criteria, defining one or more limiting scenarios based on the design envelope, and determining a safety margin in at least one figure-of-merit for the system based on the design envelope and the acceptance criteria.
Apparatuses for reducing or eliminating Type 1 LOCAs in a nuclear reactor vessel. A nuclear reactor including a nuclear reactor core comprising a fissile material, a pressure vessel containing the nuclear reactor core immersed in primary coolant disposed in the pressure vessel, and an isolation valve assembly including, an isolation valve vessel having a single open end with a flange, a spool piece having a first flange secured to a wall of the pressure vessel and a second flange secured to the flange of the isolation valve vessel, a fluid flow line passing through the spool piece to conduct fluid flow into or out of the first flange wherein a portion of the fluid flow line is disposed in the isolation valve vessel, and at least one valve disposed in the isolation valve vessel and operatively connected with the fluid flow line.
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p. ex. tenant compte des contraintes thermiques le tube traversant la paroi, c.-à-d. s'étendant de chaque côté
G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
G21C 19/04 - Moyens pour commander le flux du réfrigérant sur les objets manipulésMoyens pour commander le flux de réfrigérant à travers le canal à alimenter
F16K 17/00 - Soupapes ou clapets de sûretéSoupapes ou clapets d'équilibrage
G21C 19/30 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteurDispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p. ex. par extraction des produits de fission
Refueling of a nuclear reactor (40) includes removing a fuel assembly (10). The removal method includes lowering a lifting tool (80) of a crane (44) onto a top of the fuel assembly. The lowered lifting tool including a plurality of downwardly extending elements (82) that surround and vertically overlap a portion (74) of a control rod assembly (70) extending above the top of the fuel assembly. The downwardly extending elements are locked with corresponding mating features (26) 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 (42) 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.
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
15.
PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
In conjunction with a pressurized water reactor (PWR) and a pressurizer configured to control pressure in the reactor pressure vessel, a decay heat removal system comprises a pressurized passive condenser, a turbine-driven pump connected to suction water from at least one water source into the reactor pressure vessel; and steam piping configured to deliver steam from the pressurizer to the turbine to operate the pump and to discharge the delivered steam into the pressurized passive condenser. The pump and turbine may be mounted on a common shaft via which the turbine drives the pump. The at least one water source may include a refueling water storage tank (RWST) and/or the pressurized passive condenser. A pressurizer power operated relief valve may control discharge of a portion of the delivered steam bypassing the turbine into the pressurized passive condenser to control pressure in the pressurizer.
A spacer grid welding fixture comprises a frame sized to receive an assembled spacer grid comprising a first set of parallel straps and a second set of parallel straps oriented orthogonally to the first set of parallel straps, the first and second sets of parallel straps interlocked together by slots cut into the straps. A first set of grid engagement bars is placed on a first side of the spacer grid with each grid engagement bar arranged parallel with the straps of the first set of parallel straps and engaging the straps of the second set of parallel straps. A second set of grid engagement bars is placed on an opposite second side of the spacer grid with each grid engagement bar arranged parallel with the straps of the second set of parallel straps and engaging the straps of the first set of parallel straps.
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
A pellet magazine includes a plurality of pellet bores sized to receive pellets for loading into a fuel rod. A fuel rod loading system includes a plurality of pellet loading stations each designated to load a single pellet type into one or more pellet bores of the pellet magazine, a rod loading station configured to unload pellets from the pellet bores of the pellet magazine into a fuel rod, and a conveyance system configured to transport the pellet magazine to the loading stations and then to the rod loading station in a defined sequence.
In a pressurized water reactor (PWR), emergency core cooling (ECC) responds to depressurization due to a vessel penetration break at the top of the pressure vessel by draining water from a body of water through an injection line into the pressure vessel. A barrier operates concurrently with the ECC to suppress flow of liquid water from the pressure vessel out the vessel penetration break. The barrier may comprise one or more of: (1) an injection line extension passing through the central riser to drain water into the central riser; (2) openings in a lower portion of a central riser to shunt some upward flow from the central riser into a lower portion of the downcomer annulus; and (3) a surge line providing fluid communication between a pressurizer volume at the top of the pressure vessel and the remainder of the pressure vessel which directs water outboard toward the downcomer annulus.
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 1/09 - Dispositions pour la régulation de pression, c.-à-d. pressuriseurs
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 15/26 - Cyclage du fluide réfrigérant par convection, p. ex. utilisant des cheminées, utilisant des canaux divergents
19.
Control rod drive mechanism (CRDM) mounting method for pressurized water reactors
A standoff supporting a control rod drive mechanism (CRDM) in a nuclear reactor is connected to a distribution plate which provides electrical power and hydraulics. The standoff has connectors that require no action to effectuate the electrical connection to the distribution plate other than placement of the standoff onto the distribution plate. This facilitates replacement of the CRDM. In addition to the connectors, the standoff has alignment features to ensure the CRDM is connected in the correct orientation. After placement, the standoff may be secured to the distribution plate by bolts or other fasteners. The distribution plate may be a single plate that contains the electrical and hydraulic lines and also is strong enough to provide support to the CRDMs or may comprise a stack of two or more plates.
G21C 7/16 - Aménagements de conduite hydrauliques ou pneumatiques
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
A spacer grid welding fixture comprises a frame sized to receive an assembled spacer grid comprising a first set of parallel straps and a second set of parallel straps oriented orthogonally to the first set of parallel straps, the first and second sets of parallel straps interlocked together by slots cut into the straps. A first set of grid engagement bars is placed on a first side of the spacer grid with each grid engagement bar arranged parallel with the straps of the first set of parallel straps and engaging the straps of the second set of parallel straps. A second set of grid engagement bars is placed on an opposite second side of the spacer grid with each grid engagement bar arranged parallel with the straps of the second set of parallel straps and engaging the straps of the first set of parallel straps.
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
In a pressurized water reactor (PWR), emergency core cooling (ECC) responds to depressurization due to a vessel penetration break at the top of the pressure vessel by draining water from a body of water through an injection line into the pressure vessel. A barrier operates concurrently with the ECC to suppress flow of liquid water from the pressure vessel out the vessel penetration break. The barrier may comprise one or more of: (1) an injection line extension passing through the central riser to drain water into the central riser; (2) openings in a lower portion of a central riser to shunt some upward flow from the central riser into a lower portion of the downcomer annulus; and (3) a surge line providing fluid communication between a pressurizer volume at the top of the pressure vessel and the remainder of the pressure vessel which directs water outboard toward the downcomer annulus.
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 15/26 - Cyclage du fluide réfrigérant par convection, p. ex. utilisant des cheminées, utilisant des canaux divergents
22.
Pellet handling apparatus and fuel rod loading method
A pellet magazine includes a plurality of pellet bores sized to receive pellets for loading into a fuel rod. A fuel rod loading system includes a plurality of pellet loading stations each designated to load a single pellet type into one or more pellet bores of the pellet magazine, a rod loading station configured to unload pellets from the pellet bores of the pellet magazine into a fuel rod, and a conveyance system configured to transport the pellet magazine to the loading stations and then to the rod loading station in a defined sequence.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21C 19/02 - Détails des dispositions pour la manipulation
Refueling of a nuclear reactor (40) includes removing a fuel assembly (10). The removal method includes lowering a lifting tool (80) of a crane (44) onto a top of the fuel assembly. The lowered lifting tool including a plurality of downwardly extending elements (82) that surround and vertically overlap a portion (74) of a control rod assembly (70) extending above the top of the fuel assembly. The downwardly extending elements are locked with corresponding mating features (26) 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 (42) 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.
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 reactor control interface includes a home screen video display unit (VDU) displaying blocks representing functional components of a nuclear power plant and connecting arrows that connect blocks that are providing the current heat sinking path for the nuclear power plant. Directions of the connecting arrows represent the direction of heat flow along the current heat sinking path. If the current heat flow path of the plant changes, the connecting arrows are updated accordingly. Additional VDUs include: a mimic VDU displaying a mimic of a plant component; a procedures VDU displaying a stored procedure executable by the plant; a multi-trend VDU trending various plant data; and an alarms VDU displaying side-by-side alarms registries sorted by time and priority respectively. If a VDU fails, the displays are shifted to free up one VDU to present the display of the failed VDU, and one display is shifted to an additional VDU.
G21D 3/00 - Commande des installations à énergie nucléaire
G06F 3/14 - Sortie numérique vers un dispositif de visualisation
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
25.
Resistance pressure weld for nuclear reactor fuel rod tube end plug
A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.
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.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21C 19/02 - Détails des dispositions pour la manipulation
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 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
27.
Lower end fitting locknut for nuclear fuel assembly
An apparatus including a lower end fitting having a top planar surface, a bottom planar surface, a counterbore defined therebetween, an opening extending from the counterbore to the top planar surface, and a lock recess that extends both radially outwardly from the counterbore and extends inwardly into the lower end fitting from the bottom planar surface. The apparatus includes a guide tube having a lower end and an end plug configured to connect with the lower end of the guide tube. The end plug has a threaded shaft sized to pass through the opening of the lower end fitting, and a female lock nut has a deformable side wall configured to be swaged into the recess of the lower end fitting. The lock recess remains visible as viewed from the bottom planar surface of the lower end fitting when the female lock nut is fully disposed in the counterbore.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
F16B 39/02 - Blocage des vis, boulons ou écrous dans lequel le verrouillage s'effectue après vissage
F16B 23/00 - Têtes de boulons ou de vis de forme spéciale pour permettre leur rotation à l'aide d'un outil
B25B 23/00 - Parties constitutives ou accessoires des clés à écrous, clés anglaises, tournevis
28.
Combined mounting/electrical distribution plate for powering internal control rod drive mechanism (CRDM) units of a nuclear reactor
An apparatus having a nuclear reactor comprising a pressure vessel containing primary coolant water and further containing a nuclear reactor core comprising fissile material, a mounting/electrical distribution plate secured entirely within the pressure vessel and configured to be submerged in the primary coolant, a set of control rod drive mechanism (CRDM) units mounted directly on the mounting/electrical distribution plate, and a plurality of cable modules mounted in receptacles of the mounting/electrical distribution plate wherein each cable module includes mineral insulated (MI) cables connected with one or more of the CRDM units, the cable module including its MI cables being removable as a unit from the receptacle of the mounting/electrical distribution plate.
G21C 7/16 - Aménagements de conduite hydrauliques ou pneumatiques
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
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 13/00 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
G21C 17/116 - Passages ou isolateurs, p. ex. pour câbles électriques
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
A nuclear reactor comprises a nuclear reactor core disposed in a pressure vessel. An isolation valve protects a penetration through the pressure vessel. The isolation valve comprises: a mounting flange connecting with a mating flange of the pressure vessel; a valve seat formed into the mounting flange; and a valve member movable between an open position and a closed position sealing against the valve seat. The valve member is disposed inside the mounting flange or inside the mating flange of the pressure vessel. A biasing member operatively connects to the valve member to bias the valve member towards the open position. The bias keeps the valve member in the open position except when a differential fluid pressure across the isolation valve and directed outward from the pressure vessel exceeds a threshold pressure.
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 1/09 - Dispositions pour la régulation de pression, c.-à-d. pressuriseurs
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
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
F04D 13/10 - Ensembles comprenant les pompes et leurs moyens d'entraînement la pompe étant entraînée par l'électricité pour utilisation en position immergée adaptés pour l'utilisation dans les forages de mine
A nuclear reactor includes a pressure vessel and a nuclear reactor core comprising fissile material disposed inside the pressure vessel at the bottom of the pressure vessel. A secondary core containment structure includes a containment basket comprising insulation with a maximum stable temperature of at least 2200K cladded by steel. The bottom of the pressure vessel and the nuclear reactor core are disposed inside the containment basket with the containment basket spaced apart from the bottom of the pressure vessel by a clearance gap. The containment basket may comprise zirconia insulation cladded by steel. In some embodiments the clearance gap between the containment basket and the bottom of the pressure vessel is no larger than one meter. The secondary core containment structure may further comprise conduits arranged to inject water into the clearance gap between the containment basket and the bottom of the pressure vessel.
G21C 11/08 - Écrans thermiquesRevêtements thermiques, c.-à-d. pour dissiper la chaleur provenant de radiations gamma qui sans cela chaufferaient un écran biologique externe
A nuclear reactor core comprising fissile material is surrounded by a core former. The core former comprises one or more single-piece annular rings wherein each single-piece annular ring comprises neutron-reflecting material. In some embodiments the core former comprises a stack of two or more such single-piece annular rings. In some embodiments the stack of single-piece annular rings is self-supporting. In some embodiments the stack of single-piece annular rings does not include welds or fasteners securing adjacent single-piece annular rings together. A core basket may contain the nuclear reactor core and the core former, and in some embodiments an annular gap is defined between the core former and the core basket. In some embodiments the core former does not include welds and does not include fasteners.
Refueling of a nuclear reactor (40) includes removing a fuel assembly (10). The removal method includes lowering a lifting tool (80) of a crane (44) onto a top of the fuel assembly. The lowered lifting tool including a plurality of downwardly extending elements (82) that surround and vertically overlap a portion (74) of a control rod assembly (70) extending above the top of the fuel assembly. The downwardly extending elements are locked with corresponding mating features (26) 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 (42) 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.
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
34.
Extruded guide frame and manufacturing methods thereof
A control rod guide frame has a central passage of constant cross-section as a function of position along a central axis that passes through the central passage. The central passage is sized and shaped to guide a traveling assembly including at least one control rod as it moves along the central axis. The control rod guide frame comprises at least two radial guide frame sections secured around and defining the central passage. Each radial guide frame section may comprise an extruded radial guide frame section, which may be made of extruded steel. The central passage may include control rod guidance channels parallel the central axis and machined into the extruded radial guide frame sections. The at least two radial guide frame sections may be interchangeable. In some embodiments the at least two radial guide frame sections consist of between four and eight radial guide frame sections.
G21C 7/117 - Grappes de barres de commandeStructure en araignée
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 21/18 - Fabrication des éléments de commande couverts par le groupe
A pressurized water reactor (PWR) comprises a pressure vessel containing primary coolant water. A nuclear reactor core is disposed in the pressure vessel and includes a plurality of fuel assemblies. Each fuel assembly includes a plurality of fuel rods containing a fissile material. A control system includes a plurality of control rod assemblies (CRA's). Each CRA is guided by a corresponding CRA guide structure. A support element is disposed above the CRA guide structures and supports the CRA guide structures. The pressure vessel may be cylindrical, and the support element may comprise a support plate having a circular periphery supported by the cylindrical pressure vessel. The CRA guide structures suitably hang downward from the support plate. The lower end of each CRA guide structure may include alignment features that engage corresponding alignment features of the upper end of the corresponding fuel assembly.
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
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 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
36.
CRDM internal electrical connector and method of use thereof
A method including providing an internal control rod drive mechanism (CRDM) including an electric motor and a support surface including sealed electrical connectors electrically connected with the electric motor to deliver electrical power to the electrical motor, installing the internal CRDM inside a nuclear reactor, the installing including placing the support surface of the internal CRDM onto a support element inside the nuclear reactor, the placing causing sealed electrical connectors disposed on the support element to mate with the sealed electrical connectors on the support surface of the internal CRDM, wherein the nuclear reactor contains coolant water and the installing is performed with the internal CRDM submerged in the coolant water and the seals of the sealed electrical connectors of the internal CRDM and the support element are effective to prevent coolant water ingress into the sealed electrical connectors.
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 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 7/16 - Aménagements de conduite hydrauliques ou pneumatiques
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
37.
RESISTANCE PRESSURE WELD FOR NUCLEAR REACTOR FUEL ROD TUBE END PLUG
A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.
A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.
A fuel rod for a nuclear reactor, including a cladding tube having a first end with an annular end face, a second end with an annular end face, and a cylindrical body portion extending therebetween, and a first tube end plug including a front portion, an annular lip with an annular end face, and a substantially straight cylindrical body portion extending therebetween, wherein the surface area of the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are substantially equal, and the annular end face of the first end of the cladding tube and the annular end face of the annular lip of the first tube end plug are connected by a resistance pressure weld.
A shipping container comprises a tubular or cylindrical shell having a closed end and an open end, a top end-cap removably secured to the open end of the tubular or cylindrical shell, and at least one fuel assembly compartment defined inside the shell. Each fuel assembly compartment includes elastomeric sidewalls and is sized and shaped to receive an unirradiated nuclear fuel assembly through the open end of the shell. The shipping container may further include a divider component, for example having a cross-shaped cross-section with ends of the cross secured to inner walls of the shell, and the divider component and the inner walls of the shell define the fuel assembly compartments. To load, the shipping container is arranged vertically and an unirradiated nuclear fuel assembly is loaded through the open end of the shell into each compartment, after which the open end is closed off by securing the top end-cap.
A nuclear island includes a nuclear reactor, a lateral seismic restraint, and a reactor core retention cooling system. The lateral seismic restraint includes a vertically oriented pin attached to one of the bottom of the lower vessel head and the floor underneath the nuclear reactor, and a mating pin socket is attached to the other of the bottom of the lower vessel head and the floor. The reactor core retention cooling system includes one or more baffles, optionally thermally insulating material, disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head. A plenum is defined between the one or more baffles and the exterior surface of a lower portion of the reactor pressure vessel. The one or more baffles may define a lower plenum inlet surrounding the lateral seismic restraint.
A standoff supporting a control rod drive mechanism (CRDM) in a nuclear reactor is connected to a distribution plate which provides electrical power and hydraulics. The standoff has connectors that require no action to effectuate the electrical connection to the distribution plate other than placement of the standoff onto the distribution plate. This facilitates replacement of the CRDM. In addition to the connectors, the standoff has alignment features to ensure the CRDM is connected in the correct orientation. After placement, the standoff may be secured to the distribution plate by bolts or other fasteners. The distribution plate may be a single plate that contains the electrical and hydraulic lines and also is strong enough to provide support to the CRDMs or may comprise a stack of two or more plates.
G21C 7/16 - Aménagements de conduite hydrauliques ou pneumatiques
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
43.
PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
In conjunction with a pressurized water reactor (PWR) and a pressurizer configured to control pressure in the reactor pressure vessel, a decay heat removal system comprises a pressurized passive condenser, a turbine-driven pump connected to suction water from at least one water source into the reactor pressure vessel; and steam piping configured to deliver steam from the pressurizer to the turbine to operate the pump and to discharge the delivered steam into the pressurized passive condenser. The pump and turbine may be mounted on a common shaft via which the turbine drives the pump. The at least one water source may include a refueling water storage tank (RWST) and/or the pressurized passive condenser. A pressurizer power operated relief valve may control discharge of a portion of the delivered steam bypassing the turbine into the pressurized passive condenser to control pressure in the pressurizer.
Apparatuses for reducing or eliminating Type 1 LOCAs in a nuclear reactor vessel. A nuclear reactor including a nuclear reactor core comprising a fissile material, a pressure vessel containing the nuclear reactor core immersed in primary coolant disposed in the pressure vessel, and an isolation valve assembly including, an isolation valve vessel having a single open end with a flange, a spool piece having a first flange secured to a wall of the pressure vessel and a second flange secured to the flange of the isolation valve vessel, a fluid flow line passing through the spool piece to conduct fluid flow into or out of the first flange wherein a portion of the fluid flow line is disposed in the isolation valve vessel, and at least one valve disposed in the isolation valve vessel and operatively connected with the fluid flow line.
G21C 19/04 - Moyens pour commander le flux du réfrigérant sur les objets manipulésMoyens pour commander le flux de réfrigérant à travers le canal à alimenter
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p. ex. tenant compte des contraintes thermiques le tube traversant la paroi, c.-à-d. s'étendant de chaque côté
G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
G21C 19/30 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteurDispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p. ex. par extraction des produits de fission
45.
Riser cone apparatus to provide compliance between reactor components and minimize reactor coolant bypass flow
A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.
G21C 13/028 - Joints, p. ex. pour les cuves de pression ou les enceintes de confinement
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
G21C 13/04 - Dispositions pour l'expansion et la contraction
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
G21C 15/02 - 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
A spacer grid includes interlocked straps comprising metal sheets or plates welded together to define a spacer grid having a top and bottom. The interlocked straps define a plurality of cells comprising vertical passages connecting the top and bottom of the spacer grid. The cells include: upper dimples proximate to the top of the spacer grid and distal from the mid-plane of the spacer grid; lower dimples proximate to the bottom of the spacer grid and distal from the mid-plane of the spacer grid; cantilevered upper springs having fuel rod engagement surfaces proximate to the top of the spacer grid and distal from the mid-plane of the spacer grid; and cantilevered lower springs having fuel rod engagement surfaces proximate to the bottom of the spacer grid and distal from the mid-plane of the spacer grid.
An apparatus and method for system safety analysis evaluation is provided, the apparatus including processing circuitry configured for generating a calculation matrix for a system, generating a plurality of models based on the calculation matrix, performing a benchmarking or convolution analysis of the plurality of models, identifying a design envelope based on the benchmarking or convolution analysis, deriving uncertainty models from the benchmarking or convolution analysis, deriving an assessment judgment based on the uncertainty models and acceptance criteria, defining one or more limiting scenarios based on the design envelope, and determining a safety margin in at least one figure-of-merit for the system based on the design envelope and the acceptance criteria.
An apparatus and method for system safety analysis evaluation is provided, the apparatus including processing circuitry configured for generating a calculation matrix for a system, generating a plurality of models based on the calculation matrix, performing a benchmarking or convolution analysis of the plurality of models, identifying a design envelope based on the benchmarking or convolution analysis, deriving uncertainty models from the benchmarking or convolution analysis, deriving an assessment judgment based on the uncertainty models and acceptance criteria, defining one or more limiting scenarios based on the design envelope, and determining a safety margin in at least one figure-of-merit for the system based on the design envelope and the acceptance criteria.
An apparatus and method for system safety analysis evaluation is provided, the apparatus including processing circuitry configured for generating a calculation matrix for a system, generating a plurality of models based on the calculation matrix, performing a benchmarking or convolution analysis of the plurality of models, identifying a design envelope based on the benchmarking or convolution analysis, deriving uncertainty models from the benchmarking or convolution analysis, deriving an assessment judgment based on the uncertainty models and acceptance criteria, defining one or more limiting scenarios based on the design envelope, and determining a safety margin in at least one figure-of-merit for the system based on the design envelope and the acceptance criteria.
In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (12, 14, 16), a nuclear reactor core (10) disposed in the pressure vessel, and a vertically oriented hollow central riser (36) disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) (30) disposed in the pressure vessel includes vertical tubes (32) arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet (50) and a steam outlet (52). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
F22B 1/02 - Méthodes de production de vapeur caractérisées par le genre de chauffage par exploitation de l'énergie thermique contenue dans une source chaude
G21D 1/00 - Détails des installations à énergie nucléaire
A nuclear reactor includes a pressure vessel, and a control rod assembly including at least one movable control rod comprising a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a first portion comprising a first material having a first density at room temperature, and a second portion comprising a second material having a second density at room temperature that is greater than the first density. In some embodiments the coupling includes a connecting rod including a hollow or partially hollow connecting rod tube comprising a first material having a first density and a filler disposed in the hollow or partially hollow connecting rod tube, the filler comprising a second material having a second density greater than the first density.
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
A control rod guide frame comprises a self supporting stack of two or more columnar elements defining a central passage. The columnar elements may include mating features that mate at abutments between adjacent columnar elements of the stack. The control rod guide frame is suitably used in conjunction with a control rod drive mechanism (CRDM) operatively connected with at least one control rod, and a nuclear reactor core, in which the CRDM moves the at least one control rod into and out of the nuclear reactor core under guidance of the control rod guide frame. In another embodiment, a control rod guide frame comprises a stack of two or more columnar elements defining a central passage having a constant cross-section as a function of position along the central passage. In another embodiment, a control rod guide frame comprises an extruded columnar element providing continuous control rod guidance.
G21C 7/117 - Grappes de barres de commandeStructure en araignée
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 21/18 - Fabrication des éléments de commande couverts par le groupe
A valve assembly includes a flange connected to a vessel penetration of a reactor pressure vessel of a nuclear reactor. A valve is disposed inside the flange or protrudes from the flange into the vessel penetration. The valve includes a valve seat and a movable valve member positioned so that pressure inside the reactor pressure vessel urges the movable valve member against the valve seat to close the valve. The valve assembly further includes a plenum having an inlet via which the plenum can be pressurized to apply pressure to the movable valve member that urges the movable valve member away from the valve seat to open the valve. The plenum may be defined in part by a surface of the movable valve member. The valve assembly preferably does not include a valve actuator.
G21C 19/307 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteurDispositions pour enlever un matériau fluent du cœur du réacteur avec purification continue du matériau fluent en circulation, p. ex. par extraction des produits de fission spécialement adaptés pour des liquides
G21C 15/14 - 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 des conduits servant au passage d'un fluide chaudAménagement 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 des conduits comprenant des appareils auxiliaires, p. ex. pompes, caméras
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
F16K 15/18 - Soupapes, clapets ou valves de retenue à mécanisme de commandeSoupape de retenue et soupape à mécanisme de commande combinées
A valve assembly and systems for coupling pressure vessels are provided. The valve assembly comprises: a flange configured to connect with a vessel penetration of a reactor pressure vessel of a nuclear reactor; a valve body inside the flange or arranged to protrude from the flange into the vessel penetration; a valve comprising a valve seat and a movable valve member, the valve inside the valve body with the movable valve member positioned so that pressure inside the reactor pressure vessel urges the movable valve member along a direction of travel against the valve seat to close the valve. A plenum is defined between the valve body and the movable valve member which has an inlet. The plenum is configured such that pressurization of the plenum via the inlet urges the movable valve member away from the valve seat along the direction of travel to open the valve.
F16K 1/12 - Soupapes ou clapets, c.-à-d. dispositifs obturateurs dont l'élément de fermeture possède au moins une composante du mouvement d'ouverture ou de fermeture perpendiculaire à la surface d'obturation à corps de soupape profilé autour duquel le fluide s'écoule quand la soupape est ouverte
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
A valve assembly includes a flange connected to a vessel penetration of a reactor pressure vessel of a nuclear reactor. A valve is disposed inside the flange or protrudes from the flange into the vessel penetration. The valve includes a valve seat and a movable valve member positioned so that pressure inside the reactor pressure vessel urges the movable valve member against the valve seat to close the valve. The valve assembly further includes a plenum having an inlet via which the plenum can be pressurized to apply pressure to the movable valve member that urges the movable valve member away from the valve seat to open the valve. The plenum may be defined in part by a surface of the movable valve member. The valve assembly preferably does not include a valve actuator.
F16K 1/12 - Soupapes ou clapets, c.-à-d. dispositifs obturateurs dont l'élément de fermeture possède au moins une composante du mouvement d'ouverture ou de fermeture perpendiculaire à la surface d'obturation à corps de soupape profilé autour duquel le fluide s'écoule quand la soupape est ouverte
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
A nuclear reactor includes a nuclear reactor core comprising fissile material disposed in a reactor pressure vessel having vessel penetrations that exclusively carry flow into the nuclear reactor and at least one vessel penetration that carries flow out of the nuclear reactor. An integral isolation valve (IIV) system includes passive IIVs each comprising a check valve built into a forged flange and not including an actuator, and one or more active IIVs each comprising an active valve built into a forged flange and including an actuator. Each vessel penetration exclusively carrying flow into the nuclear reactor is protected by a passive IIV whose forged flange is directly connected to the vessel penetration. Each vessel penetration carrying flow out of the nuclear reactor is protected by an active IIV whose forged flange is directly connected to the vessel penetration. Each active valve may be a normally closed valve.
G21C 19/28 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteurDispositions pour enlever un matériau fluent du cœur du réacteur
57.
Integral isolation valve systems for loss of coolant accident protection
A nuclear reactor includes a nuclear reactor core comprising fissile material disposed in a reactor pressure vessel having vessel penetrations that exclusively carry flow into the nuclear reactor and at least one vessel penetration that carries flow out of the nuclear reactor. An integral isolation valve (IIV) system includes passive IIVs each comprising a check valve built into a forged flange and not including an actuator, and one or more active IIVs each comprising an active valve built into a forged flange and including an actuator. Each vessel penetration exclusively carrying flow into the nuclear reactor is protected by a passive IIV whose forged flange is directly connected to the vessel penetration. Each vessel penetration carrying flow out of the nuclear reactor is protected by an active IIV whose forged flange is directly connected to the vessel penetration. Each active valve may be a normally closed valve.
A nuclear reactor includes a nuclear reactor core comprising fissile material disposed in a reactor pressure vessel having vessel penetrations that exclusively carry flow into the nuclear reactor and at least one vessel penetration that carries flow out of the nuclear reactor. An integral isolation valve (IIV) system includes passive IIVs each comprising a check valve built into a forged flange and not including an actuator, and one or more active IIVs each comprising an active valve built into a forged flange and including an actuator. Each vessel penetration exclusively carrying flow into the nuclear reactor is protected by a passive IIV whose forged flange is directly connected to the vessel penetration. Each vessel penetration carrying flow out of the nuclear reactor is protected by an active IIV whose forged flange is directly connected to the vessel penetration. Each active valve may be a normally closed valve.
G21C 15/14 - 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 des conduits servant au passage d'un fluide chaudAménagement 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 des conduits comprenant des appareils auxiliaires, p. ex. pompes, caméras
G21C 15/10 - 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 du réflecteur ou de l'écran thermique
A nuclear reactor includes a reactor core comprising fissile material disposed in a reactor pressure vessel. A radiological containment contains the nuclear reactor. A containment compartment contains the radiological containment. A heat sink includes a chimney configured to develop an upward-flowing draft in response to heated fluid flowing into a lower portion of the chimney. A fluid conduit is arranged to receive fluid from the containment compartment and to discharge into the chimney. A filter may be provided, with the fluid conduit including a first fluid conduit arranged to receive fluid from the containment compartment and to discharge into an inlet of the filter, and a second fluid conduit arranged to receive fluid from an outlet of the filter and to discharge into the chimney. As the draft is developed passively, there is no need for a blower or pump configured to move fluid through the fluid conduit.
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
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
A nuclear reactor includes a reactor pressure vessel and a nuclear reactor core comprising fissile material disposed in a lower portion of the reactor pressure vessel. The lower portion of the reactor pressure vessel is disposed in a reactor cavity. An annular neutron stop is located at an elevation above the uppermost elevation of the nuclear reactor core. The annular neutron stop comprises neutron absorbing material filling an annular gap between the reactor pressure vessel and the wall of the reactor cavity. The annular neutron stop may comprise an outer neutron stop ring attached to the wall of the reactor cavity, and an inner neutron stop ring attached to the reactor pressure vessel. An excore instrument guide tube penetrates through the annular neutron stop, and a neutron plug comprising neutron absorbing material is disposed in the tube at the penetration through the neutron stop.
A nuclear reactor includes a reactor core disposed in a reactor pressure vessel. A radiological containment contains the nuclear reactor and includes a concrete floor located underneath the nuclear reactor. An ex vessel corium retention system includes flow channels embedded in the concrete floor located underneath the nuclear reactor, an inlet in fluid communication with first ends of the flow channels, and an outlet in fluid communication with second ends of the flow channels. In some embodiments the inlet is in fluid communication with the interior of the radiological containment at a first elevation and the outlet is in fluid communication with the interior of the radiological containment at a second elevation higher than the first elevation. The radiological containment may include a reactor cavity containing a lower portion of the pressure vessel, wherein the concrete floor located underneath the nuclear reactor is the reactor cavity floor.
A nuclear reactor including a lateral seismic restraint with a vertically oriented pin attached to the lower vessel head and a mating pin socket attached to the floor. Thermally insulating materials are disposed alongside the exterior surface of a lower portion of the reactor pressure vessel including at least the lower vessel head.
A nuclear reactor is surrounded by a reactor radiological containment structure. Depressurization lines running from the reactor automatically vent the reactor to the containment structure or to a compartment in the containment structure when a low pressure condition exists in the reactor. The depressurization lines include biased-open passive valves and actively actuated isolation valves arranged in series.
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an integral pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the integral pressurizer. The drive shaft passes through a vessel penetration of the pressure vessel that is at least large enough for the impeller to pass through.
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 1/09 - Dispositions pour la régulation de pression, c.-à-d. pressuriseurs
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
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
F04D 13/10 - Ensembles comprenant les pompes et leurs moyens d'entraînement la pompe étant entraînée par l'électricité pour utilisation en position immergée adaptés pour l'utilisation dans les forages de mine
A shipping container containing an unirradiated nuclear fuel assembly is lifted off the ground by operating a crane to raise a lifting tool comprising a winch. The lifting tool is connected with the shipping container by a rigging line connecting with the shipping container at a lifting point located on the shipping container between the top and bottom of the shipping container, and by winch cabling connecting with the shipping container at the top of the shipping container. The shipping container is reoriented by operating the winch to adjust the length of the winch cabling so as to rotate the shipping container about the lifting point. Shortening the winch cabling rotates the shipping container about the lifting point from a horizontal orientation to a vertical orientation, while lengthening the winch cabling rotates the shipping container about the lifting point from the vertical orientation to the horizontal orientation.
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p. ex. dispositifs de transport
B66C 1/12 - Élingues comportant chaînes, fils métalliques, cordes ou bandesFilets
B66C 1/62 - Éléments ou dispositifs de prise de la charge adjoints aux mécanismes de levage, de descente ou de halage, ou adaptés pour être utilisés avec ces mécanismes et transmettant les efforts à des articles ou à des groupes d'articles par moyens mécaniques comportant des organes de saisie ayant une forme complémentaire de celle des objets à manipuler
B66C 13/08 - Dispositifs auxiliaires pour commander les mouvements des charges suspendues ou pour empêcher le câble de prendre du mou pour déposer les charges selon un orientement ou dans une position donnés
A nuclear reactor includes a pressure vessel, and a control rod assembly including at least one movable control rod comprising a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a first portion comprising a first material having a first density at room temperature, and a second portion comprising a second material having a second density at room temperature that is greater than the first density. In some embodiments the coupling includes a connecting rod including a hollow or partially hollow connecting rod tube comprising a first material having a first density and a filler disposed in the hollow or partially hollow connecting rod tube, the filler comprising a second material having a second density greater than the first density.
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
A pressurized water reactor (PWR) includes a vertical cylindrical pressure vessel having a lower portion containing a nuclear reactor core and a vessel head defining an internal pressurizer. A reactor coolant pump (RCP) mounted on the vessel head includes an impeller inside the pressure vessel, a pump motor outside the pressure vessel, and a vertical drive shaft connecting the motor and impeller. The drive shaft does not pass through the internal pressurizer. A central riser may be disposed concentrically inside the pressure vessel, and the RCP impels primary coolant downward into a downcomer annulus between the central riser and the pressure vessel. A steam generator may be disposed in the downcomer annulus and spaced apart from with the impeller by an outlet plenum. A manway may access the outlet plenum so tube plugging can be performed on the steam generator via access through the manway without removing the RCP.
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 15/243 - Cyclage du fluide réfrigérant pour des liquides
F04D 7/08 - Pompes adaptées à la manipulation de liquides particuliers, p. ex. par choix de matériaux spéciaux pour les pompes ou pièces de pompe du type centrifuge les fluides étant radioactifs
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
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 19/28 - Dispositions pour introduire un matériau fluent à l'intérieur du cœur du réacteurDispositions pour enlever un matériau fluent du cœur du réacteur
A nuclear reactor is surrounded by a reactor radiological containment structure. Depressurization lines running from the reactor automatically vent the reactor to the containment structure or to a compartment in the containment structure when a low pressure condition exists in the reactor. The depressurization lines include biased-open passive valves and actively actuated isolation valves arranged in series.
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
70.
PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel
In conjunction with a pressurized water reactor (PWR) and a pressurizer configured to control pressure in the reactor pressure vessel, a decay heat removal system comprises a pressurized passive condenser, a turbine-driven pump connected to suction water from at least one water source into the reactor pressure vessel; and steam piping configured to deliver steam from the pressurizer to the turbine to operate the pump and to discharge the delivered steam into the pressurized passive condenser. The pump and turbine may be mounted on a common shaft via which the turbine drives the pump. The at least one water source may include a refueling water storage tank (RWST) and/or the pressurized passive condenser. A pressurizer power operated relief valve may control discharge of a portion of the delivered steam bypassing the turbine into the pressurized passive condenser to control pressure in the pressurizer.
In a pressurized water reactor (PWR), emergency core cooling (ECC) responds to depressurization due to a vessel penetration break at the top of the pressure vessel by draining water from a body of water through an injection line into the pressure vessel. A barrier operates concurrently with the ECC to suppress flow of liquid water from the pressure vessel out the vessel penetration break. The barrier may comprise one or more of: (1) an injection line extension passing through the central riser to drain water into the central riser; (2) openings in a lower portion of a central riser to shunt some upward flow from the central riser into a lower portion of the downcomer annulus; and (3) a surge line providing fluid communication between a pressurizer volume at the top of the pressure vessel and the remainder of the pressure vessel which directs water outboard toward the downcomer annulus.
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
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
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.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
73.
CRDM designs with separate SCRAM latch engagement and locking
A control rod drive mechanism (CRDM) includes a lifting rod supporting a control rod and a holding mechanism comprising an electromagnetic circuit with magnetic poles drawn together when the electromagnetic circuit is energized to hold the lifting rod. The hold is released upon de-energizing the electromagnetic circuit. A translation mechanism linearly translates the lifting rod held by the holding mechanism. The holding mechanism may include a non-magnetic spacer between the magnetic poles that defines a gap between the drawn together magnetic poles. The translation mechanism may include latches configured to engage an upper end of the lifting rod, and the holding mechanism draws the magnetic poles together to hold the latches engaged with the upper end of the lifting rod. A four-bar cam assembly may be used to cam the latches closed in response to a vertical actuation force applied to the cam bars.
In an illustrative embodiment, a pressurized water nuclear reactor (PWR) includes a pressure vessel (12, 14, 16), a nuclear reactor core (10) disposed in the pressure vessel, and a vertically oriented hollow central riser (36) disposed above the nuclear reactor core inside the pressure vessel. A once-through steam generator (OTSG) (30) disposed in the pressure vessel includes vertical tubes (32) arranged in an annular volume defined by the central riser and the pressure vessel. The OTSG further includes a fluid flow volume surrounding the vertical tubes and having a feedwater inlet (50) and a steam outlet (52). The PWR has an operating state in which feedwater injected into the fluid flow volume at the feedwater inlet is converted to steam by heat emanating from primary coolant flowing inside the tubes of the OTSG, and the steam is discharged from the fluid flow volume at the steam outlet.
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
75.
REFUELING WATER STORAGE TANK (RWST) WITH TAILORED PASSIVE EMERGENCY CORE COOLING (ECC) FLOW
A nuclear reactor comprises a pressure vessel containing a nuclear reactor core. A reactor core cooling system comprises a standpipe including a plurality of orifices in fluid communication with a refueling water storage tank (RWST) to drain water from the RWST into the standpipe, and an injection line configured to drain water from the standpipe to the pressure vessel. In some embodiments the standpipe is disposed in the RWST, while in other embodiments the standpipe is disposed outside of the RWST and cross-connection pipes connect the plurality of orifices with the RWST. The reactor core cooling system may further comprise a valve configured to control flow through one orifice of the plurality of orifices in fluid communication with the RWST based on water level in the standpipe. The valve may comprise a float valve having its float disposed in the standpipe.
A nuclear reactor comprises a pressure vessel containing a nuclear reactor core. A reactor core cooling system comprises a standpipe including a plurality of orifices in fluid communication with a refueling water storage tank (RWST) to drain water from the RWST into the standpipe, and an injection line configured to drain water from the standpipe to the pressure vessel. In some embodiments the standpipe is disposed in the RWST, while in other embodiments the standpipe is disposed outside of the RWST and cross-connection pipes connect the plurality of orifices with the RWST. The reactor core cooling system may further comprise a valve configured to control flow through one orifice of the plurality of orifices in fluid communication with the RWST based on water level in the standpipe. The valve may comprise a float valve having its float disposed in the standpipe.
A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.
A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.
A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.
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
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
80.
CRDM WITH SEPARATE SCRAM LATCH ENGAGEMENT AND LOCKING
A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.
A nuclear reactor comprises a pressure vessel containing a nuclear reactor core. A reactor core cooling system comprises a standpipe including a plurality of orifices in fluid communication with a refueling water storage tank (RWST) to drain water from the RWST into the standpipe, and an injection line configured to drain water from the standpipe to the pressure vessel. In some embodiments the standpipe is disposed in the RWST, while in other embodiments the standpipe is disposed outside of the RWST and cross-connection pipes connect the plurality of orifices with the RWST. The reactor core cooling system may further comprise a valve configured to control flow through one orifice of the plurality of orifices in fluid communication with the RWST based on water level in the standpipe. The valve may comprise a float valve having its float disposed in the standpipe.
A control rod drive mechanism (CRDM) configured to latch onto the lifting rod of a control rod assembly and including separate latch engagement and latch holding mechanisms. A CRDM configured to latch onto the lifting rod of a control rod assembly and including a four-bar linkage closing the latch, wherein the four-bar linkage biases the latch closed under force of gravity.
A shipping container comprises a tubular or cylindrical shell having a closed end and an open end, a top end-cap removably secured to the open end of the tubular or cylindrical shell, and at least one fuel assembly compartment defined inside the shell. Each fuel assembly compartment includes elastomeric sidewalls and is sized and shaped to receive an unirradiated nuclear fuel assembly through the open end of the shell. The shipping container may further include a divider component, for example having a cross-shaped cross-section with ends of the cross secured to inner walls of the shell, and the divider component and the inner walls of the shell define the fuel assembly compartments. To load, the shipping container is arranged vertically and an unirradiated nuclear fuel assembly is loaded through the open end of the shell into each compartment, after which the open end is closed off by securing the top end-cap.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21F 5/012 - Râteliers pour éléments combustibles dans le récipient
G21F 5/08 - Amortisseurs de chocs spécialement adaptés à ces récipients
G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p. ex. dispositifs de transport
A spacer grid includes intersecting straps defining cells with springs and dimples arranged to hold fuel rods passing through the cells. The direction of the springs switches at a switch point in the spacer grid that is not at the center of the spacer grid. The intersecting straps may include a first set of mutually parallel straps including a first transition strap and a second set of mutually parallel straps including a second transition strap, with the second set intersecting the first set. The springs of the first set of mutually parallel straps face away from the first transition strap, and the springs of the second set of mutually parallel straps face away from the second transition strap. The outer straps in some embodiments include dimples but not springs.
A spacer grid includes intersecting straps defining cells with springs and dimples arranged to hold fuel rods passing through the cells. The springs are dual cantilevered springs with a bridge section between the distal end of the spring and the base. The distal portion of the spring is less stiff than the bridge section. The bridge section creates a bump which acts as a stop or travel limiter to prevent loss of grip force due to excessive spring deflection.
A pressurized water reactor (PWR) comprises a pressure vessel containing primary coolant water. A nuclear reactor core is disposed in the pressure vessel and includes a plurality of fuel assemblies. Each fuel assembly includes a plurality of fuel rods containing a fissile material. A control system includes a plurality of control rod assemblies (CRA's). Each CRA is guided by a corresponding CRA guide structure. A support element is disposed above the CRA guide structures and supports the CRA guide structures. The pressure vessel may be cylindrical, and the support element may comprise a support plate having a circular periphery supported by the cylindrical pressure vessel. The CRA guide structures suitably hang downward from the support plate. The lower end of each CRA guide structure may include alignment features that engage corresponding alignment features of the upper end of the corresponding fuel assembly.
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
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
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 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
A control room for a nuclear power plant including two or more nuclear reactor units includes a central workstation providing monitoring capability for both nuclear reactor units, a first operator at the controls (OATC) workstation in front of and to one side of the central workstation providing monitoring and control capabilities for the first nuclear reactor unit, a second OATC workstation in front of and to the other side of the central workstation providing monitoring and control capabilities for the second nuclear reactor unit, and a common control workstation directly in front of the central workstation providing monitoring and control capabilities for systems serving both the first nuclear reactor unit and the second nuclear reactor unit. The central and common control workstations do not provide control capabilities for either nuclear reactor unit. The common control workstation does not include any control capabilities that must be performed by a licensed operator.
G21D 3/00 - Commande des installations à énergie nucléaire
G21D 3/08 - Régulation de différents paramètres dans l'installation
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
A reactor control interface includes a home screen video display unit (VDU) displaying blocks representing functional components of a nuclear power plant and connecting arrows that connect blocks that are providing the current heat sinking path for the nuclear power plant. Directions of the connecting arrows represent the direction of heat flow along the current heat sinking path. If the current heat flow path of the plant changes, the connecting arrows are updated accordingly. Additional VDUs include: a mimic VDU displaying a mimic of a plant component; a procedures VDU displaying a stored procedure executable by the plant; a multi-trend VDU trending various plant data; and an alarms VDU displaying side-by-side alarms registries sorted by time and priority respectively. If a VDU fails, the displays are shifted to free up one VDU to present the display of the failed VDU, and one display is shifted to an additional VDU.
An internal control rod drive mechanism (CRDM) including an electric motor is disposed in a nuclear reactor and further includes a support surface with sealed electrical connectors electrically connected with the electric motor power the motor. The internal CRDM is disposed on a support element secured inside the nuclear reactor. The support element includes sealed electrical connectors mating with the sealed electrical connectors on the support surface of the internal CRDM to power the electric motor. The sealed electrical connectors may be sealed glass, ceramic, or glass-ceramic connectors welded onto the ends of the Ml cables extending from the motor. Springs, are disposed between the mating sealed electrical connectors of the support element and the support surface. A purge line is integrated with each mated connection.
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
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
A nuclear reactor has a core installed on a lower core plate and formed from multiple fuel assemblies, each fuel assembly including a structural cage assembly. The structural cage assembly has an upper end fitting, mid grids, and a lower end fitting (LEF). The LEF positions the fuel assembly using four locating pins located at each corner of the LEF. The pins position the fuel assembly laterally by mating with receiving holes in the lower core plate. The locating pins have a chamfered tip with a flat end. The chamfered tip allows for a greater positioning margin when installing the fuel assembly in the core by guiding the pins into holes in the lower core plate, and the flat tip provides strength and stability in case the assembly is inadvertently rested on the tip of the pin instead of the LEF pads.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 15/02 - 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
93.
POWER DISTRIBUTION PLATE FOR POWERING INTERNAL CONTROL ROD DRIVE MECHANISM (CRDM) UNITS
A power distribution plate (PDP) sits on top of a support plate. Control rod drive mechanism (CRDM) units are mounted on top of the PDP, but the PDP is incapable of supporting the weight of the CRDM units and instead transfers the load to a support plate. The PDP has receptacles which receive cable modules each including mineral insulated (Ml) cables, the Ml cables being connected with the CRDM units. The PDP may further include a set of hydraulic lines underlying the cable modules and connected with the CRDM units. The cable modules in their receptacles define conduits or raceways for their Ml cables and for any underlying hydraulic lines.
H01B 3/10 - Isolateurs ou corps isolants caractérisés par le matériau isolantEmploi de matériaux spécifiés pour leurs propriétés isolantes ou diélectriques composés principalement de substances inorganiques oxydes métalliques
H01B 7/20 - Tubes métalliques, p. ex. gaines de plomb
94.
AUXILIARY CONDENSER SYSTEM FOR DECAY HEAT REMOVAL IN A NUCLEAR REACTOR SYSTEM
A nuclear reactor includes an internal steam generator and a nuclear core disposed in a containment structure. A condenser is disposed outside the containment structure, and includes a condenser inlet line tapping off a steam line connected to the steam generator outside the containment structure, and a condensate injection line conveying condensate from the condenser to the integral steam generator. Isolation valves are located outside the containment structure on a feedwater line, the steam line, and the condensate injection line. The valves have an operating configuration in which the isolation valves on the feedwater and steam lines are open and the isolation valve on the condensate injection line is closed, and a heat removal configuration in which the isolation valves on the feedwater and steam lines are closed and the isolation valve on the condensate injection line is open.
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
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
95.
Riser cone apparatus to provide compliance between reactor components and minimize reactor coolant bypass flow
A riser cone has a lower end sized to engage a cylindrical lower riser section of a nuclear reactor and an upper end sized to engage a cylindrical upper riser section of the nuclear reactor. The riser cone defines a compression sealing ring that is compressed between the lower riser section and the upper riser section in the assembled nuclear reactor. In some embodiments the riser cone comprises: a lower element defining the lower end of the riser cone; an upper element defining the upper end of the riser cone; and a compliance spring compressed between the lower element and the upper element. In some embodiments the riser cone comprises a frustoconical compression sealing ring accommodating a reduced diameter of the upper riser section as compared with the diameter of the lower riser section.
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
G21C 13/04 - Dispositions pour l'expansion et la contraction
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 13/028 - Joints, p. ex. pour les cuves de pression ou les enceintes de confinement
G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
96.
Suspended upper internals for compact nuclear reactor including a mid-hanger plate
A pressure vessel comprises an upper vessel section and a lower vessel section. A nuclear reactor core comprising fissile material is disposed the lower vessel section. Upper internals are disposed in the lower vessel section above the nuclear reactor core and are mounted on a suspended support assembly including a plurality of hanger plates connected by tie rods. The upper internals include at least guide frames and internal control rod drive mechanisms (CRDMs) with CRDM motors. The plurality of hanger plates includes a mid-hanger plate that is not the uppermost plate of the plurality of hanger plates and is not the lowermost plate of the plurality of hanger plates. The internal CRDMs are disposed above the mid-hanger plate, the guide frames are disposed below the mid-hanger plate, and the mid-hanger plate engages both the internal CRDMs and the guide frames.
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
An internal control rod drive mechanism (CRDM) including an electric motor is disposed in a nuclear reactor and further includes a support surface with sealed electrical connectors electrically connected with the electric motor power the motor. The internal CRDM is disposed on a support element secured inside the nuclear reactor. The support element includes sealed electrical connectors mating with the sealed electrical connectors on the support surface of the internal CRDM to power the electric motor. The sealed electrical connectors may be sealed glass, ceramic, or glass-ceramic connectors welded onto the ends of the MI cables extending from the motor. Springs, are disposed between the mating sealed electrical connectors of the support element and the support surface. A purge line is integrated with each mated connection.
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
H05K 13/00 - Appareils ou procédés spécialement adaptés à la fabrication ou l'ajustage d'ensembles de composants électriques
G21C 7/16 - Aménagements de conduite hydrauliques ou pneumatiques
98.
Integral pressurized water reactor with compact upper internals assembly
An integral pressurized water reactor (PWR) comprises: a cylindrical pressure vessel including an upper vessel section and a lower vessel section joined by a mid-flange; a cylindrical central riser disposed concentrically inside the cylindrical pressure vessel and including an upper riser section disposed in the upper vessel section and a lower riser section disposed in the lower vessel section; steam generators disposed inside the cylindrical pressure vessel in the upper vessel section; a reactor core comprising fissile material disposed inside the cylindrical pressure vessel in the lower vessel section; and control rod drive mechanism (CRDM) units disposed inside the cylindrical pressure vessel above the reactor core and in the lower vessel section. There is no vertical overlap between the steam generators and the CRDM units.
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
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 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
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 includes a nuclear reactor core comprising fissile material and a pressure vessel containing the nuclear reactor immersed in primary coolant water at an operating pressure. The pressure vessel has a vessel penetration passing through a wall of the pressure vessel. An electrical feedthrough seals the vessel penetration and has an outside electrical connector mounted at the pressure vessel. The outside electrical connector is at atmospheric pressure. The electrical feedthrough may include a flange disposed inside the pressure vessel and sealing against an inside surface of the wall of the pressure vessel. The outside electrical connector of the electrical feedthrough may be inset into the wall of the pressure vessel.
G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p. ex. tenant compte des contraintes thermiques le tube traversant la paroi, c.-à-d. s'étendant de chaque côté
G21C 7/12 - Moyens pour amener les éléments de commande dans la position désirée
G21C 17/116 - Passages ou isolateurs, p. ex. pour câbles électriques
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
A control rod assembly including at least one movable control rod including a neutron absorbing material, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a terminal element engaged with a connecting rod of the CRDM and the at least one moveable control rod, and a kinetic energy absorbing element supported by the terminal element for absorbing kinetic energy during a SCRAM event, the kinetic energy absorbing element configured to act between the terminal element and an upper plate of an associated fuel assembly.
G21C 9/027 - Moyens pour effectuer une réduction très rapide du facteur de réactivité dans des conditions défectueuses, p. ex. fusible pour réacteur par le mouvement rapide d'un solide, p. ex. de boulets
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