A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor core, inserted into a sodium removal machine having a receiver, a cleaning vessel, and an elevator. A cleaning fluid is applied to the cleaning vessel and fuel assembly, and the fuel assembly is flushed with water while in the cleaning vessel. The cleaning vessel is at least partially submerged in the spent fuel pool during cleaning to provide passive heat removal. The cleaning vessel is lowered by an elevator into the spent fuel pool. The fuel assembly may then be loaded into a rack and/or a cask for long-term storage.
2.
FUEL HANDLING SYSTEM, LAYOUT, AND PROCESS FOR NUCLEAR REACTOR
A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor core, inserted into a sodium removal machine having a receiver, a cleaning vessel, and an elevator. A cleaning fluid is applied to the cleaning vessel and fuel assembly, and the fuel assembly is flushed with water while in the cleaning vessel. The cleaning vessel is at least partially submerged in the spent fuel pool during cleaning to provide passive heat removal. The cleaning vessel is lowered by an elevator into the spent fuel pool. The fuel assembly may then be loaded into a rack and/or a cask for long-term storage.
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 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/24 - Dispositions pour avoir accès à l'intérieur de l'enceinte sous pression pendant le fonctionnement du réacteur par utilisation d'une enceinte auxiliaire qui est temporairement scellée à l'enceinte sous pression
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21F 5/00 - Récipients blindés portatifs ou transportables
G21C 19/07 - Râteliers de stockagePiscines de stockage
A fast neutron nuclear reactor contains a nuclear reactor core having an array of device locations. Some device locations in the nuclear reactor core contain fissile and fertile nuclear fuel assembly devices. One or more other device locations in the nuclear reactor core contain Doppler reactivity augmentation devices that amplify the negativity of the Doppler reactivity coefficient within the nuclear reactor core. In some implementations, a Doppler reactivity augmentation device can also reduce the coolant temperature coefficient within the nuclear reactor core. Accordingly, a Doppler reactivity augmentation device contributes to a more stable nuclear reactor core.
G21C 7/06 - Commande de la réaction nucléaire par application de matériau absorbant les neutrons, c.-à-d. matériau avec section efficace d'absorption excédant largement la section efficace de réflexion
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 3/42 - Emploi de substances spécifiées comme combustibles pour réacteurs
G21C 7/02 - Commande de la réaction nucléaire par utilisation des propriétés autorégulatrices des matériaux du réacteur
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
Energy storage plants; structural parts and fittings for
nuclear power plants; nuclear power plants; nuclear
reactors. Demonstration of products in the fields of energy
production, nuclear energy and nuclear technology;
government advocacy, namely, promoting new and emerging
nuclear technology; new product commercialization services
in the fields of energy production, nuclear energy and
nuclear technology; promoting the benefits of nuclear
technology and nuclear energy to governments and
professionals in the energy industry; providing online
commercial information and news in the field of carbon-free
energy initiatives; advertising services to promote public
awareness of nuclear energy by means of public advocacy.
A nuclear reactor includes a heat exchanger that transfers thermal energy from a primary reactor coolant to a secondary coolant. The heat exchanger is formed with a hot flow channel, a cold flow channel, and a porous layer between the hot flow channel and the cold flow channel. The porous layer may be thermally insulative to reduce the efficiency of thermal energy transfer from the hot flow channel to the cold flow channel. The porous layer may have a control gas passed therethrough that can be tailored to control the thermal energy transfer through the porous layer. The control gas can be tested for leakage within the heat exchanger. The control gas may also be used to sequester fission or activation products.
Disclosed embodiments include fuel assemblies, methods of making a fuel element, and methods of using a fuel element. A fuel element includes fuel, a fuel liner, and a cladding. The liner may be formed of one, two, three, or more layers of different materials, including different alloys have a different primary metallic component. The cladding may likewise be formed of one, two, three, or more layers of different materials. The different materials may include different alloys, different compositions, and/or different alloys in which the primary constituent of the alloy is a different material.
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p. ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
7.
METHOD OF CONSTRUCTING A NUCLEAR REACTOR HAVING REACTOR CORE AND CONTROL ELEMENTS SUPPORTED BY REACTOR VESSEL HEAD
A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.
F04B 17/03 - Pompes caractérisées par leur combinaison avec des machines motrices ou moteurs particuliers qui les entraînent ou par leur adaptation à ceux-ci entraînées par des moteurs 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 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 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
G21C 13/04 - Dispositions pour l'expansion et la contraction
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
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
This document describes a method for reducing the corrosivity of certain magnesium salts. The salt product resulting from the method exhibits reduced corrosion of steels that come into contact with the salt relative to salt compositions that are not so treated. This makes such treated salts more efficient coolant salts as they will require less equipment replacement over time. The method uses magnesium metal to reduce unwanted impurities in the salts the reduced impurities are then removed as either gas or precipitate from the now purified salt. Without being bound to one particular theory, it is believed that the reduction of the level of impurities in the salt results in a salt with substantially reduced corrosiveness to steel.
(1) Energy storage plants; structural parts and fittings for nuclear power plants; nuclear power plants; nuclear reactors. (1) Demonstration of products in the fields of energy production, nuclear energy and nuclear technology; government advocacy, namely, promoting new and emerging nuclear technology; new product commercialization services in the fields of energy production, nuclear energy and nuclear technology; promoting the benefits of nuclear technology and nuclear energy to governments and professionals in the energy industry; providing online commercial information and news in the field of carbon-free energy initiatives; advertising services to promote public awareness of nuclear energy by means of public advocacy.
Demonstration of products in the fields of energy production, nuclear energy and nuclear technology; Government advocacy, namely, promoting new and emerging nuclear technology; New product commercialization services in the fields of energy production, nuclear energy and nuclear technology; Promoting the benefits of nuclear technology and nuclear energy to governments and professionals in the energy industry; Promoting public awareness of carbon free energy initiatives, namely, providing online information, news, and commentary in the field of carbon-free energy initiatives; Public advocacy to promote awareness of nuclear energy (Based on Use in Commerce) Energy storage plants; Structural parts and fittings for nuclear power plants; (Based on Intent To Use) ; Nuclear power plants; Nuclear reactors
13.
MODULAR MANUFACTURE, DELIVERY, AND ASSEMBLY OF NUCLEAR REACTOR BUILDING SYSTEMS
A nuclear reactor is constructed in sub-modules and super modules which are manufactured, packaged, and shipped to a construction site. At least some of the modules are packaged in suitable shielding containers or portions of containers, which may be steel. The modules are assembled on-site, and some of the modules remain within their respective shipping containers after assembly. One or more of the shipping containers may be used as concrete forms to support the pouring of concrete in between selected modules. The concrete may be used for structural support, shielding, or both.
E04H 5/02 - Bâtiments ou groupes de bâtiments à des fins industrielles, p. ex. pour centrales énergétiques ou usines
E04B 1/16 - Structures formées à partir de matériaux en vrac, p. ex. de béton, coulés ou formés de façon analogue, sur place, avec ou sans emploi d'éléments additionnels, tels que coffrages permanents ou infrastructures à recouvrir du matériau porteur de la charge
G21C 3/16 - Détails de structure à l'intérieur de l'enveloppe
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 3/328 - Disposition relative des éléments dans le réseau
An in-vessel fuel transfer machine may be permanently affixed to a nuclear reactor and remain in place during power operations. The in-vessel fuel transfer machine may include a pantograph machine that positions a grapple in order to access any fuel socket location within the core and move any of the core assemblies between the core, an in-vessel fuel storage area, and a fuel elevator. The grapple may be positioned through a combination of movements, such as, rotating a rotating plug assembly, rotating the in-vessel fuel transfer machine, extending the pantograph arms, and shuttling the grapple along a leg. The grapple may be compliant to accommodate deformed core assemblies and may be configured to pivot to more closely align to an eccentric core assembly handling socket or be moveable in a horizontal plane to accommodate a deformed core assembly during insertion or withdrawal.
G21C 19/26 - Dispositions pour enlever les éléments combustibles ou les éléments de commande grippés ou endommagésDispositions pour déplacer les parties cassées de ceux-ci
B25J 9/10 - Manipulateurs à commande programmée caractérisés par des moyens pour régler la position des éléments manipulateurs
B25J 13/08 - Commandes pour manipulateurs au moyens de dispositifs sensibles, p. ex. à la vue ou au toucher
G21C 19/105 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande à éléments de couplage effectuant un mouvement de serrage ou d'extension
G21C 19/16 - Couloirs ou tubes articulés ou télescopiques pour le raccordement aux canaux dans le cœur du réacteur
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
15.
METHOD FOR ONLINE RADIOISOTOPE MEASUREMENT FOR FAILED FUEL CHARACTERIZATION IN PRIMARY SODIUM SYSTEMS
A failed fuel pin emits cesium into the primary sodium coolant and xenon into the cover gas in a reactor vessel (402). A pipe (408) containing radioactive liquid sodium accepts flowing primary sodium from the reactor vessel. A radiation detector (416) is positioned adjacent the pipe such that gamma radiation emitted from the pipe can be measured. The pipe may be isolated to increase detection limits by allowing short-lived isotopes to decay. The isotopic ratio of 137Cs/134Cs can be measured, which can be used to determine the burnup of a fuel assembly from within the core, and therefore, the failed fuel assembly can be identified based at least in part on the burnup. Further, mass spectrometry may be used to measure the ratio of a stable and unstable xenon isotope. The identification techniques may be used in conjunction to quickly identify a failed fuel assembly in-situ and during reactor operation.
A failed fuel pin emits cesium into the primary sodium coolant and xenon into the cover gas in a reactor vessel. A pipe containing radioactive liquid sodium accepts flowing primary sodium from the reactor vessel. A radiation detector is positioned adjacent the pipe such that gamma radiation emitted from the pipe can be measured. The pipe may be isolated to increase detection limits by allowing short-lived isotopes to decay. The isotopic ratio of 137Cs/134Cs can be measured, which can be used to determine the burnup of a fuel assembly from within the core, and therefore, the failed fuel assembly can be identified based at least in part on the burnup. Further, mass spectrometry may be used to measure the ratio of a stable and unstable xenon isotope. The identification techniques may be used in conjunction to quickly identify a failed fuel assembly in-situ and during reactor operation.
G21C 17/022 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides
A nuclear reactor core includes a plurality of core assemblies. The core assemblies have a cooperating structure formed at one or more load pads that mechanically couple the plurality of core assemblies together to limit relative motion between core assemblies in a kinematically determinate way. A shear key on one core assembly is configured to fit in a tab slot on an adjacent core assembly. Motion of one core assembly is transferred to a second core assembly and the core assemblies move together.
In a sodium fast reactor, a bypass pipe is fluidly coupled to the primary sodium pump discharge and diverts a portion of the primary sodium coolant to an instrument assembly. The bypass pipe routes flowing sodium upward toward the reactor head where it fluidly couples to the instrument assembly. The instrument assembly includes an instrument tank and selectively swappable instrument modules. The instrument modules can be configured to measure flow, pressure, temperature, and fluid level, among other things. The instrument assembly is located relatively close to the reactor head and close to the sodium level in the sodium pool and is accessible from above the reactor head for quick and efficient removal and replacement of the entire instrument assembly or individual instruments.
G21C 17/025 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides pour la surveillance de réfrigérants constitués par des métaux liquides
G21C 17/032 - Mesure ou surveillance du débit de réfrigérant
G21C 17/035 - Dispositifs de détection du niveau de réfrigérant ou du modérateur
In a sodium fast reactor, a bypass pipe is fluidly coupled to the primary sodium pump discharge and diverts a portion of the primary sodium coolant to an instrument assembly. The bypass pipe routes flowing sodium upward toward the reactor head where it fluidly couples to the instrument assembly. The instrument assembly includes an instrument tank and selectively swappable instrument modules. The instrument modules can be configured to measure flow, pressure, temperature, and fluid level, among other things. The instrument assembly is located relatively close to the reactor head and close to the sodium level in the sodium pool and is accessible from above the reactor head for quick and efficient removal and replacement of the entire instrument assembly or individual instruments.
G21C 17/025 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants ou de modérateurs liquides pour la surveillance de réfrigérants constitués par des métaux liquides
20.
INTERLOCKING FUEL ASSEMBLY STRUCTURE FOR CORE REACTIVITY CONTROL
A nuclear reactor core includes a plurality of core assemblies. The core assemblies have a cooperating structure formed at one or more load pads that mechanically couple the plurality of core assemblies together to limit relative motion between core assemblies in a kinematically determinate way. A shear key on one core assembly is configured to fit in a tab slot on an adjacent core assembly. Motion of one core assembly is transferred to a second core assembly and the core assemblies move together.
G21C 19/105 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande à éléments de couplage effectuant un mouvement de serrage ou d'extension
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/26 - Dispositions pour enlever les éléments combustibles ou les éléments de commande grippés ou endommagésDispositions pour déplacer les parties cassées de ceux-ci
22.
IN-VESSEL CORE COMPONENT HANDLING SYSTEMS AND METHODS
An in-vessel fuel transfer machine may be permanently affixed to a nuclear reactor and remain in place during power operations. The in-vessel fuel transfer machine may include a pantograph machine that positions a grapple in order to access any fuel socket location within the core and move any of the core assemblies between the core, an in-vessel fuel storage area, and a fuel elevator. The grapple may be positioned through a combination of movements, such as, rotating a rotating plug assembly, rotating the in-vessel fuel transfer machine, extending the pantograph arms, and shuttling the grapple along a leg. The grapple may be compliant to accommodate deformed core assemblies and may be configured to pivot to more closely align to an eccentric core assembly handling socket or be moveable in a horizontal plane to accommodate a deformed core assembly during insertion or withdrawal.
G21C 19/105 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande à éléments de couplage effectuant un mouvement de serrage ou d'extension
G21C 19/18 - Appareils pour porter les éléments combustibles à l'aire de charge du réacteur, p. ex. depuis un emplacement de stockage
G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
G21C 19/26 - Dispositions pour enlever les éléments combustibles ou les éléments de commande grippés ou endommagésDispositions pour déplacer les parties cassées de ceux-ci
Energy storage plants; nuclear power plants and structural
parts and fittings therefor; nuclear reactors. Demonstration of products in the fields of energy
production, nuclear energy and nuclear technology;
Government advocacy, namely, promoting new and emerging
nuclear technology; new product commercialization services
in the fields of energy production, nuclear energy and
nuclear technology; promoting the benefits of nuclear
technology and nuclear energy to governments and
professionals in the energy industry; providing business
information via a website in the field of carbon-free energy
initiatives; public advocacy to promote awareness of nuclear
energy.
A masking element with an opening is disposed on the side of a core support structure. A flow stack wall defines a plurality of inlets. At least one inlet aligns with the masking element opening when the flow stack is mated with the masking element. A flow control assembly within the flow stack is configured to restrict flow of fluid within the flow stack.
A masking element with an opening is disposed on the side of a core support structure. A flow stack wall defines a plurality of inlets. At least one inlet aligns with the masking element opening when the flow stack is mated with the masking element. A flow control assembly within the flow stack is configured to restrict flow of fluid within the flow stack.
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
A method of removing cesium vapor from a cover gas stream in a nuclear reactor includes the steps of oxidizing the cesium vapor in the cover gas stream to yield cesium oxide particles and removing the cesium oxide particles using a particle filter. The method yields a filtered cover gas having zero to about 2% of the cesium vapor content of the initial cover gas stream, representing a reduction of at least about 98 percent.
B01D 53/82 - Procédés en phase solide avec des réactifs à l'état stationnaire
G21C 19/303 - 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 gaz
B01D 39/20 - Autres substances filtrantes autoportantes en substance inorganique, p. ex. papier d'amiante ou substance filtrante métallique faite de fils métalliques non-tissés
B01D 53/46 - Élimination des composants de structure définie
30.
OXIDATION OF CESIUM AS METHOD FOR REMOVING CESIUM VAPOR FROM COVER GAS IN NUCLEAR REACTORS
A method of removing cesium vapor from a cover gas stream in a nuclear reactor includes the steps of oxidizing the cesium vapor in the cover gas stream to yield cesium oxide particles and removing the cesium oxide particles using a particle filter. The method yields a filtered cover gas having zero to about 2% of the cesium vapor content of the initial cover gas stream, representing a reduction of at least about 98 percent.
A nuclear reactor is configured with an intermediate coolant loop for transferring thermal energy from the reactor core for a useful purpose. The intermediate coolant loop includes a bypass flowpath with an air heat exchanger for dumping reactor heat during startup and/or shutdown. A fluidic diode along the bypass flowpath asymmetrically restricts flow across the bypass flowpath, inhibiting flow in a first flow direction during a full power operating condition and allowing a relatively uninhibited flow in a second direction during a startup and/or shut down low power operating condition.
(1) Energy storage plants; nuclear power plants and structural parts and fittings therefor; nuclear reactors. (1) Demonstration of products in the fields of energy production, nuclear energy and nuclear technology; Government advocacy, namely, promoting new and emerging nuclear technology; new product commercialization services in the fields of energy production, nuclear energy and nuclear technology; promoting the benefits of nuclear technology and nuclear energy to governments and professionals in the energy industry; providing business information via a website in the field of carbon-free energy initiatives; public advocacy to promote awareness of nuclear energy.
Demonstration of products in the fields of energy production, nuclear energy and nuclear technology; Government advocacy, namely, promoting new and emerging nuclear technology; New product commercialization services in the fields of energy production, nuclear energy and nuclear technology; Promoting the benefits of nuclear technology and nuclear energy to governments and professionals in the energy industry; Providing online information, news, and commentary in the field of carbon-free energy initiatives; Public advocacy to promote awareness of nuclear energy
A fuel element has a ratio of area of fissionable nuclear fuel in a cross-section of the tubular fuel element perpendicular to the longitudinal axis to total area of the interior volume in the cross-section of the tubular fuel element that varies with position along the longitudinal axis. The ratio can vary with position along the longitudinal axis between a minimum of 0.30 and a maximum of 1.0. Increasing the ratio above and below the peak burn-up location associated with conventional systems reduces the peak burn-up and flattens and shifts the burn-up distribution, which is preferably Gaussian. The longitudinal variation can be implemented in fuel assemblies using fuel bodies, such as pellets, rods or annuli, or fuel in the form of metal sponge and meaningfully increases efficiency of fuel utilization.
Embodiments of methods for improving mesophase pitch for carbon fiber production using supercritical carbon dioxide are described. The methods improve the relative amount and quality of mesophase pitch in feedstocks, such as coal tar, already having at least some mesophase pitch. One particular method includes performing a sCO2/toluene extraction on the coal tar to obtain a toluene insoluble fraction of the coal tar; mixing the toluene insoluble fraction with sCO2 to obtain a sCO2/toluene insoluble fraction mixture; and extruding the sCO2/toluene insoluble fraction mixture, thereby separating the sCO2 from the toluene insoluble fraction to obtain fibers of mesophase pitch.
C10C 3/08 - Traitement du brai, de l'asphalte, du bitume par extraction sélective
C01B 32/05 - Préparation ou purification du carbone non couvertes par les groupes , , ,
D01F 9/15 - Filaments de carboneAppareils spécialement adaptés à leur fabrication par décomposition de filaments organiques à partir de brai ou de résidus de distillation à partir de brai de charbon
39.
HIGH ASSAY, LOW ENRICHED URANIUM DECONVERSION PROCESS
A novel semi-batch process for deconverting high assay low enriched uranium (HALEU) from its uranium hexafluoride state to uranium dioxide and other chemical states useful as feeds for nuclear fuel in a nuclear reactor is provided. The semi-batch process enables the use of equipment that is small enough, and production rates that are low enough, to meet nuclear criticality safety restraints for HALEU, while enabling the safe, dependable, and economical production of HALEU feed for nuclear fuel at a nominal capacity of up to about 20 MTU (metric tons of uranium metal) per year per deconversion reactor.
A novel semi-batch process for deconverting high assay low enriched uranium (HALEU) from its uranium hexafluoride state to uranium dioxide and other chemical states useful as feeds for nuclear fuel in a nuclear reactor is provided. The semi-batch process enables the use of equipment that is small enough, and production rates that are low enough, to meet nuclear criticality safety restraints for HALEU, while enabling the safe, dependable, and economical production of HALEU feed for nuclear fuel at a nominal capacity of up to about 20 MTU (metric tons of uranium metal) per year per deconversion reactor.
A novel semi-batch process for deconverting high assay low enriched uranium (HALEU) from its uranium hexafluoride state to uranium dioxide and other chemical states useful as feeds for nuclear fuel in a nuclear reactor is provided. The semi-batch process enables the use of equipment that is small enough, and production rates that are low enough, to meet nuclear criticality safety restraints for HALEU, while enabling the safe, dependable, and economical production of HALEU feed for nuclear fuel at a nominal capacity of up to about 20 MTU (metric tons of uranium metal) per year per deconversion reactor.
A nuclear fuel assembly is constructed with fuel assembly components that are wire wrapped and positioned in hexagonal rings within a fuel assembly duct. The fuel assembly components positioned in an outermost ring of the fuel assembly are wire wrapped with a pitch that is shorter than fuel assembly components positioned at an interior ring of the fuel assembly. The shorter pitch at the outer ring of the fuel assembly increases pressure drop of a coolant fluid at the edge and corner subchannels and thereby reduces the temperature gradient across the fuel assembly, which provides a higher output temperature of the nuclear reactor without substantially increasing peak temperature of the fuel cladding.
E04H 5/02 - Bâtiments ou groupes de bâtiments à des fins industrielles, p. ex. pour centrales énergétiques ou usines
G21C 3/16 - Détails de structure à l'intérieur de l'enveloppe
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
E04B 1/16 - Structures formées à partir de matériaux en vrac, p. ex. de béton, coulés ou formés de façon analogue, sur place, avec ou sans emploi d'éléments additionnels, tels que coffrages permanents ou infrastructures à recouvrir du matériau porteur de la charge
G21C 3/328 - Disposition relative des éléments dans le réseau
A vaporizer includes an outer tube configured to receive a flow of heated gas and an inner tube disposed at least partially within the outer tube. The inner tube is spaced apart from the outer tube such that the flow of heated gas is channeled through an annular space therebetween. The vaporizer also includes a crucible disposed at least partially within the inner tube. The crucible is extendable and retractable relative to the inner tube and within the outer tube. The crucible is configured to hold a molten metal such that a surface area of the molten metal exposed to the flow of heated gas is adjustable based on the position of the crucible relative to the inner tube. A heater is configured to vaporize the molten material and the vapor mixes with the flow of heated gas.
G21C 17/028 - Dispositifs ou dispositions pour la surveillance du réfrigérant ou du modérateur pour la surveillance de réfrigérants gazeux
B01B 1/00 - ÉbullitionAppareils à ébullition en vue d'applications physiques ou chimiques
B01J 8/02 - Procédés chimiques ou physiques en général, conduits en présence de fluides et de particules solidesAppareillage pour de tels procédés avec des particules immobiles, p. ex. dans des lits fixes
B05C 11/11 - Cuves ou autres récipients à liquides ou autres matériaux fluides
C23C 14/14 - Matériau métallique, bore ou silicium
G01N 27/626 - Recherche ou analyse des matériaux par l'emploi de moyens électriques, électrochimiques ou magnétiques en recherchant l'ionisation des gaz, p. ex. des aérosolsRecherche ou analyse des matériaux par l'emploi de moyens électriques, électrochimiques ou magnétiques en recherchant les décharges électriques, p. ex. l'émission cathodique utilisant la chaleur pour ioniser un gaz
44.
FUEL-CLADDING CHEMICAL INTERACTION RESISTANT NUCLEAR FUEL ELEMENTS AND METHODS FOR MANUFACTURING THE SAME
This disclosure describes fuel-cladding chemical interaction (FCCI) resistant nuclear fuel elements and their manufacturing techniques. The nuclear fuel elements include two or more layers of different materials (i.e., adjacent barriers are of different base materials) provided on a steel cladding to reduce the effects of FCCI between the cladding and the nuclear material. Depending on the embodiment, a layer may be the structural element (i.e., a layer thick enough to provide more than 50% of the strength of the overall component consisting of the cladding and the barriers) or may be more appropriately described as a liner or coating that is applied in some fashion to a surface of the structural component (e.g., to the cladding, or to a structural form of the fuel).
G21C 3/20 - Détails de structure à l'intérieur de l'enveloppe avec revêtement sur le combustible ou sur l'intérieur de l'enveloppeDétails de structure à l'intérieur de l'enveloppe avec une intercouche non active entre l'enveloppe et le matériau actif
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
G21C 21/14 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par placage dans un fluide
45.
METHODS AND SYSTEMS FOR IMPROVED TEST FUEL REACTOR
A simple nuclear reactor in which most of the reflector material is outside of the reactor vessel is described. The reactor vessel is a cylinder that contains all of the fuel salt and a displacement component, which may be a reflector, in the upper section of the reactor vessel. Other than the displacement component, the reflector elements including a radial reflector and a bottom reflector are located outside the vessel. The salt flows around the outside surface of the displacement component through a downcomer heat exchange duct defined by the exterior of the displacement component and the interior surface of the reactor vessel. This design reduces the overall size of the reactor vessel for a given volume of salt relative to designs with internal radial or bottom reflectors.
A nuclear reactor is designed to couple the load path of control elements with the reactor core, thus reducing opportunity for differential movement between the control elements and the reactor core. A core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The core barrel can be mounted to a reactor vessel head. Movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
G21C 13/04 - Dispositions pour l'expansion et la contraction
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
G21C 5/10 - Moyens pour supporter la structure complète
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
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 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 15/247 - Cyclage du fluide réfrigérant pour des liquides pour des métaux liquides
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 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 15/12 - 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
47.
Fission product getter formed by additive manufacturing
A getter element includes a getter material reactive with a fission product contained within a stream of liquid and/or gas exiting a fuel assembly of a nuclear reactor. At least one transmission pathway passes through the getter element that is sufficiently sized to maintain a flow of the input stream through the getter element at above a selected flow level. At least one transmission pathway includes a reaction surface area sufficient to uptake a pre-identified quantity of the fission product.
G21C 3/17 - Moyens de stockage ou de fixation de gaz dans des éléments combustibles
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p. ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
48.
MODIFIED LOW POWER, FAST SPECTRUM MOLTEN FUEL REACTOR DESIGNS HAVING IMPROVED NEUTRONICS
A simple nuclear reactor in which most of the reflector material is outside of the reactor vessel is described. The reactor vessel is a cylinder that contains all of the fuel salt and a displacement component, which may be a reflector, in the upper section of the reactor vessel. Other than the displacement component, the reflector elements including a radial reflector and a bottom reflector are located outside the vessel. The salt flows around the outside surface of the displacement component through a downcomer heat exchange duct defined by the exterior of the displacement component and the interior surface of the reactor vessel. This design reduces the overall size of the reactor vessel for a given volume of salt relative to designs with internal radial or bottom reflectors.
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
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 7/32 - Commande de la réaction nucléaire par variation du courant de réfrigérant à travers le cœur
G21C 11/06 - Écrans réflecteurs, c.-à-d. pour minimiser la perte de neutrons
G21C 15/04 - 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 matériau fissile ou surrégénérateur
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
G21D 7/04 - Dispositions pour la production directe d'énergie électrique à partir de réactions de fusion ou de fission utilisant des éléments thermo-électriques
G21C 3/24 - Éléments combustibles avec un matériau fissile ou surrégénérateur sous forme fluide à l'intérieur d'une enveloppe non active
G21C 5/10 - Moyens pour supporter la structure complète
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
G21C 15/253 - Cyclage du fluide réfrigérant pour des gaz, p. ex. ventilateurs
49.
MODIFIED LOW POWER, FAST SPECTRUM MOLTEN FUEL REACTOR DESIGNS HAVING IMPROVED NEUTRONICS
A simple nuclear reactor in which most of the reflector material is outside of the reactor vessel is described. The reactor vessel is a cylinder that contains all of the fuel salt and a displacement component, which may be a reflector, in the upper section of the reactor vessel. Other than the displacement component, the reflector elements including a radial reflector and a bottom reflector are located outside the vessel. The salt flows around the outside surface of the displacement component through a downcomer heat exchange duct defined by the exterior of the displacement component and the interior surface of the reactor vessel. This design reduces the overall size of the reactor vessel for a given volume of salt relative to designs with internal radial or bottom reflectors.
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 3/24 - Éléments combustibles avec un matériau fissile ou surrégénérateur sous forme fluide à l'intérieur d'une enveloppe non active
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21C 5/10 - Moyens pour supporter la structure complète
G21C 7/32 - Commande de la réaction nucléaire par variation du courant de réfrigérant à travers le cœur
G21C 11/06 - Écrans réflecteurs, c.-à-d. pour minimiser la perte de neutrons
G21C 15/04 - 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 matériau fissile ou surrégénérateur
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
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
G21C 15/253 - Cyclage du fluide réfrigérant pour des gaz, p. ex. ventilateurs
G21D 7/04 - Dispositions pour la production directe d'énergie électrique à partir de réactions de fusion ou de fission utilisant des éléments thermo-électriques
50.
FUEL HANDLING SYSTEM, LAYOUT, AND PROCESS FOR NUCLEAR REACTOR
A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor core, inserted into a sodium removal machine having a receiver, a cleaning vessel, and an elevator. A cleaning fluid is applied to the cleaning vessel and fuel assembly, and the fuel assembly is flushed with water while in the cleaning vessel. The cleaning vessel is at least partially submerged in the spent fuel pool during cleaning to provide passive heat removal. The cleaning vessel is lowered by an elevator into the spent fuel pool. The fuel assembly may then be loaded into a rack and/or a cask for long-term storage.
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21C 19/08 - Moyens pour le chauffage des éléments combustibles avant leur introduction dans le cœurMoyens pour le chauffage ou le refroidissement des éléments combustibles après leur extraction du cœur
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
51.
THORIUM PEROXIDE-BASED GENERATORS FOR AC-225 GENERATION
The actinium generator described herein is based on peroxide precipitation of thorium from its daughter products radium and actinium. In this system, the “actinium generator” is a quantity of solid thorium peroxide stored under a cover solution. The thorium peroxide is stored as a suspension to allow for the buildup of the decay products radium and actinium in the suspension. The suspension is then treated with a peroxide solution and the solid and liquid phases are separated. The thorium remains in the solid peroxide form while the soluble actinium and radium are removed with the liquid phase in a rinsing step. After rinsing, an amount of the rinsing solution is retained with the thorium peroxide solid as a fresh cover solution to form another suspension for storage. This new suspension is then stored to allow actinium and radium to again build up in the suspension for a subsequent separation cycle.
Embodiments of methods for improving mesophase pitch for carbon fiber production using supercritical carbon dioxide are described. The methods improve the relative amount and quality of mesophase pitch in feedstocks, such as coal tar, already having at least some mesophase pitch. One particular method includes performing a sCO2/toluene extraction on the coal tar to obtain a toluene insoluble fraction of the coal tar; mixing the toluene insoluble fraction with sCO2 to obtain a sCO2/toluene insoluble fraction mixture; and extruding the sCO2/toluene insoluble fraction mixture, thereby separating the sCO2 from the toluene insoluble fraction to obtain fibers of mesophase pitch.
C10C 3/08 - Traitement du brai, de l'asphalte, du bitume par extraction sélective
D01F 9/15 - Filaments de carboneAppareils spécialement adaptés à leur fabrication par décomposition de filaments organiques à partir de brai ou de résidus de distillation à partir de brai de charbon
C01B 32/05 - Préparation ou purification du carbone non couvertes par les groupes , , ,
53.
THORIUM PEROXIDE-BASED GENERATOR FOR AC-225 GENERATION
The actinium generator described herein is based on peroxide precipitation of thorium from its daughter products radium and actinium. In this system, the "actinium generator" is a quantity of solid thorium peroxide stored under a cover solution. The thorium peroxide is stored, as a suspension to allow for the buildup of the decay products radium and actinium in the suspension. The suspension is then treated with a peroxide solution and the solid and liquid phases are separated. The thorium remains in the solid peroxide form while the soluble actinium and radium are removed with the liquid phase in a rinsing step. After rinsing, an amount of the rinsing solution is retained with the thorium peroxide solid as a fresh cover solution to form another suspension for storage. This new suspension is then stored to allow actinium and radium to again build up in the suspension for a subsequent separation cycle.
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
G21G 1/00 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs
54.
THORIUM PEROXIDE-BASED GENERATOR FOR AC-225 GENERATION
The actinium generator described herein is based on peroxide precipitation of thorium from its daughter products radium and actinium. In this system, the "actinium generator" is a quantity of solid thorium peroxide stored under a cover solution. The thorium peroxide is stored, as a suspension to allow for the buildup of the decay products radium and actinium in the suspension. The suspension is then treated with a peroxide solution and the solid and liquid phases are separated. The thorium remains in the solid peroxide form while the soluble actinium and radium are removed with the liquid phase in a rinsing step. After rinsing, an amount of the rinsing solution is retained with the thorium peroxide solid as a fresh cover solution to form another suspension for storage. This new suspension is then stored to allow actinium and radium to again build up in the suspension for a subsequent separation cycle.
G21G 1/00 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
Radiation cured composite materials are greatly improved by enhancing the fiber to matrix bond by prewetting the fibers with an interface resin that has a curing agent mixed in with the interface resin. Furthermore, radiation curing the composite material at or near an expected operating temperature of the composite material improves the mechanical properties of the material by reducing thermally induced strains and stresses caused by thermally curing a material and subsequently cooling the material. Adding an interface resin with a curing agent to the fibers allows relatively thick parts, a must faster curing process, a wide variety of inexpensive and easily workable molding materials, the ability to maintain tight tolerances and reduce or eliminate springback, and a radiation cured material that approaches or exceeds the material characteristics of thermally cured composite materials.
In one aspect, the technology relates to a method of producing Ac, the method including preparing a phosphate-modified titania material to produce an ion-exchange material, contacting a solution including 229Th with the ion-exchange material to produce a Th-loaded titania material, eluting the Th-loaded titania material with a wash solution to produce an eluted solution containing eluted compounds including 225Ac, concentrating the eluted solution to generate eluted compounds including the 225Ac, and separating the 225Ac from the eluted compounds.
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
G21G 4/08 - Sources radioactives autres que les sources de neutrons caractérisées par des aspects de leur structure spécialement adaptées aux applications médicales
In one aspect, the technology relates to a method of producing Ac, the method including preparing a phosphate-modified titania material to produce an ion-exchange material, contacting a solution including 229Th with the ion-exchange material to produce a Th-loaded titania material, eluting the Th-loaded titania material with a wash solution to produce an eluted solution containing eluted compounds including 225Ac, concentrating the eluted solution to generate eluted compounds including the 225Ac, and separating the 225Ac from the eluted compounds.
C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
G21G 4/08 - Sources radioactives autres que les sources de neutrons caractérisées par des aspects de leur structure spécialement adaptées aux applications médicales
G21G 1/00 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs
59.
ZAMAK STABILIZATION OF SPENT SODIUM-COOLED REACTOR FUEL ASSEMBLIES
Methods and systems for stabilizing spent fuel assemblies from sodium-cooled nuclear reactors using Zamak are described herein. It has been determined that there is a synergism between Zamak and sodium that allows Zamak to form thermally-conductive interface with the sodium-wetted surfaces of the fuel assemblies. In the method, one or more spent fuel assemblies are removed from the sodium coolant pool and placed in a protective sheath. The remaining volume of the sheath is then filled with liquid Zamak. To a certain extent Zamak will dissolve and alloy with sodium remaining on the fuel assemblies. Excess sodium that remains undissolved is displaced from the sheath by the Zamak fill. The Zamak is then cooled until solid and the sheath sealed. The resulting Zamak-stabilized spent fuel assembly is calculated to have sufficient internal thermal conductivity to allow it to be stored and transported without the need for liquid cooling.
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21D 1/00 - Détails des installations à énergie nucléaire
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
60.
Zamak stabilization of spent sodium-cooled reactor fuel assemblies
Methods and systems for stabilizing spent fuel assemblies from sodium-cooled nuclear reactors using Zamak are described herein. It has been determined that there is a synergism between Zamak and sodium that allows Zamak to form thermally-conductive interface with the sodium-wetted surfaces of the fuel assemblies. In the method, one or more spent fuel assemblies are removed from the sodium coolant pool and placed in a protective sheath. The remaining volume of the sheath is then filled with liquid Zamak. To a certain extent Zamak will dissolve and alloy with sodium remaining on the fuel assemblies. Excess sodium that remains undissolved is displaced from the sheath by the Zamak fill. The Zamak is then cooled until solid and the sheath sealed. The resulting Zamak-stabilized spent fuel assembly is calculated to have sufficient internal thermal conductivity to allow it to be stored and transported without the need for liquid cooling.
C22C 18/04 - Alliages à base de zinc avec l'aluminium comme second constituant majeur
G21F 1/08 - MétauxAlliagesCermets, c.-à-d. mélanges frittés de céramiques et métaux
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
61.
ZAMAK STABILIZATION OF SPENT SODIUM-COOLED REACTOR FUEL ASSEMBLIES
Methods and systems for stabilizing spent fuel assemblies from sodium-cooled nuclear reactors using Zamak are described herein. It has been determined that there is a synergism between Zamak and sodium that allows Zamak to form thermally-conductive interface with the sodium-wetted surfaces of the fuel assemblies. In the method, one or more spent fuel assemblies are removed from the sodium coolant pool and placed in a protective sheath. The remaining volume of the sheath is then filled with liquid Zamak. To a certain extent Zamak will dissolve and alloy with sodium remaining on the fuel assemblies. Excess sodium that remains undissolved is displaced from the sheath by the Zamak fill. The Zamak is then cooled until solid and the sheath sealed. The resulting Zamak-stabilized spent fuel assembly is calculated to have sufficient internal thermal conductivity to allow it to be stored and transported without the need for liquid cooling.
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21D 1/00 - Détails des installations à énergie nucléaire
05 - Produits pharmaceutiques, vétérinaires et hygièniques
Produits et services
(1) Radioisotopes for medical purposes; Diagnostic and therapeutic radioisotopes and radiochemicals for medical purposes, namely for use in diagnostics and targeted therapy for cancer patients and radio chemistry research.
A nuclear reactor includes a heat exchanger that transfers thermal energy from a primary reactor coolant to a secondary coolant. The heat exchanger is formed with a hot flow channel, a cold flow channel, and a porous layer between the hot flow channel and the cold flow channel. The porous layer may be thermally insulative to reduce the efficiency of thermal energy transfer from the hot flow channel to the cold flow channel. The porous layer may have a control gas passed therethrough that can be tailored to control the thermal energy transfer through the porous layer. The control gas can be tested for leakage within the heat exchanger. The control gas may also be used to sequester fission or activation products.
F28D 15/00 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations
A nuclear reactor includes a heat exchanger that transfers thermal energy from a primary reactor coolant to a secondary coolant. The heat exchanger is formed with a hot flow channel, a cold flow channel, and a porous layer between the hot flow channel and the cold flow channel. The porous layer may be thermally insulative to reduce the efficiency of thermal energy transfer from the hot flow channel to the cold flow channel. The porous layer may have a control gas passed therethrough that can be tailored to control the thermal energy transfer through the porous layer. The control gas can be tested for leakage within the heat exchanger. The control gas may also be used to sequester fission or activation products.
F28D 15/00 - Appareils échangeurs de chaleur dans lesquels l'agent intermédiaire de transfert de chaleur en tubes fermés passe dans ou à travers les parois des canalisations
A nuclear reactor includes a heat exchanger that transfers thermal energy from a primary reactor coolant to a secondary coolant. The heat exchanger is formed with a hot flow channel, a cold flow channel, and a porous layer between the hot flow channel and the cold flow channel. The porous layer may be thermally insulative to reduce the efficiency of thermal energy transfer from the hot flow channel to the cold flow channel. The porous layer may have a control gas passed therethrough that can be tailored to control the thermal energy transfer through the porous layer. The control gas can be tested for leakage within the heat exchanger. The control gas may also be used to sequester fission or activation products.
Configurations of molten fuel salt reactors are described that allow for active cooling of the containment vessel of the reactor by the primary coolant. Furthermore, naturally circulating reactor configurations are described in which the reactor cores are substantially frustum-shaped so that the thermal center of the reactor core is below the outlet of the primary heat exchangers. Heat exchanger configurations are described in which welded components are distanced from the reactor core to reduce the damage caused by neutron flux from the reactor. Radial loop reactor configurations are also described.
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 1/22 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés utilisant du combustible liquide ou gazeux
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
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
67.
Passive reactivity control in a nuclear fission reactor
A nuclear reactor includes a passive reactivity control nuclear fuel device located in a nuclear reactor core. The passive reactivity control nuclear fuel device includes a multiple-walled fuel chamber having an outer wall chamber and an inner wall chamber contained within the outer wall chamber. The inner wall chamber is positioned within the outer wall chamber to hold nuclear fuel in a molten fuel state within a high neutron importance region. The inner wall chamber allows at least a portion of the nuclear fuel to move in a molten fuel state to a lower neutron importance region while the molten nuclear fuel remains within the inner wall chamber as the temperature of the nuclear fuel satisfies a negative reactivity feedback expansion temperature condition. A duct contains the multiple-walled fuel chamber and flows a heat conducting fluid through the duct and in thermal communication with the outer wall chamber.
G21C 7/30 - Commande de la réaction nucléaire par déplacement du combustible du réacteur ou des éléments combustibles
G21C 3/18 - Entretoises intérieures ou autre matériau non actif à l'intérieur de l'enveloppe, p. ex. pour compenser l'expansion des barres combustibles ou pour compenser une réactivité excessive
G21C 7/02 - Commande de la réaction nucléaire par utilisation des propriétés autorégulatrices des matériaux du réacteur
68.
Anti-proliferation safeguards for nuclear fuel salts
An anti-proliferation technique is disclosed to reduce the likelihood of nuclear proliferation due to the use fissionable fuel salts. The technique includes doping the fuel salt with one or more elements (referred to herein as activation dopants) that, upon exposure to neutrons such as would occur in the fuel salt when a reactor is in operation, undergo a nuclear reaction to, directly or indirectly, form highly active “protecting isotopes” (of the same element as the activation dopant or a different element). A sufficient mass of activation dopants is used so that the Figure of Merit (FOM) of the fuel salt is decreased to below 1.0 within some target number of days of fission. This allows the FOM of the fuel salt to be controlled so that the fuel becomes too dangerous to handle before to the creation of a significant amount of weaponizable isotopes.
G21C 3/54 - Sels fondus, compositions oxydes ou hydroxydes
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
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
A nuclear fuel assembly is constructed with fuel assembly components that are wire wrapped and positioned in hexagonal rings within a fuel assembly duct. The fuel assembly components positioned in an outermost ring of the fuel assembly are wire wrapped with a pitch that is shorter than fuel assembly components positioned at an interior ring of the fuel assembly. The shorter pitch at the outer ring of the fuel assembly increases pressure drop of a coolant fluid at the edge and corner subchannels and thereby reduces the temperature gradient across the fuel assembly, which provides a higher output temperature of the nuclear reactor without substantially increasing peak temperature of the fuel cladding.
A nuclear reactor is constructed in sub-modules and super modules which are manufactured, packaged, and shipped to a construction site. At least some of the modules are packaged in suitable shielding containers or portions of containers, which may be steel. The modules are assembled on-site, and some of the modules remain within their respective shipping containers after assembly. One or more of the shipping containers may be used as concrete forms to support the pouring of concrete in between selected modules. The concrete may be used for structural support, shielding, or both.
A nuclear reactor is designed to allow efficient packing of components within the reactor vessel, such as by offsetting the core, and/or vertically stacking components. The in-vessel storage system can be separate from the support cylinder and these components can be fabricated and shipped separately and coupled together at the construction site. Furthermore, the in-vessel storage system can be located adjacent to the core rather than being located circumferentially around it, and may also be located beneath the heat exchanger to further improve packing of components within the vessel. Through these, and other changes, the delicate components can be manufactured in a manufacturing facility, assembled, and shipped by commercial transportation options without exceeding the shipping envelope.
A nuclear reactor is configured with an intermediate coolant loop for transferring thermal energy from the reactor core for a useful purpose. The intermediate coolant loop includes a bypass flowpath with an air heat exchanger for dumping reactor heat during startup and/or shutdown. A fluidic diode along the bypass flowpath asymmetrically restricts flow across the bypass flowpath, inhibiting flow in a first flow direction during a full power operating condition and allowing a relatively uninhibited flow in a second direction during a startup and/or shut down low power operating condition.
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
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 15/02 - 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
G21C 15/26 - Cyclage du fluide réfrigérant par convection, p. ex. utilisant des cheminées, utilisant des canaux divergents
73.
INERTIAL ENERGY COASTDOWN FOR ELECTROMAGNETIC PUMP
A nuclear reactor is configured with a primary coolant loop for transferring heat away from the nuclear reactor core. In a shutdown event, the primary coolant pump may stop pumping primary coolant through the reactor core, resulting in decay heat buildup within the reactor core. An inertial energy coast down system can store kinetic energy while the nuclear reactor is operating and then release the stored kinetic energy to cause the primary coolant to continue to flow through the nuclear reactor core to remove decay heat. The inertial energy coast down system may include an impeller and a flywheel having a mass. During normal reactor operation, the flowing primary coolant spins up the impeller and flywheel, and upon a shutdown event where the primary coolant pump stops pumping, the flywheel and impeller can cause the primary coolant to continue to flow during a coast down of the flywheel and impeller.
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 1/14 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur n'étant pas substantiellement pressurisé, p. ex. réacteur à pile piscine
G21C 15/247 - Cyclage du fluide réfrigérant pour des liquides pour des métaux liquides
74.
FUEL HANDLING SYSTEM, LAYOUT, AND PROCESS FOR NUCLEAR REACTOR
A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor, an inert gas is applied to the fuel assembly, moisture content in the inert gas is gradually increased as it is applied to the fuel assembly, and the fuel assembly is immersed in water. The fuel assembly is immersed relatively quickly, within about 2 hours or less, which improves safety and allows normal processing and handling equipment to care for the fuel assembly. The fuel assembly may then be loaded into a cask for long-term storage and/or disposal.
G21C 19/08 - Moyens pour le chauffage des éléments combustibles avant leur introduction dans le cœurMoyens pour le chauffage ou le refroidissement des éléments combustibles après leur extraction du cœur
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
76.
CONTAINMENT STRUCTURE AND ARRANGEMENT FOR NUCLEAR REACTOR
A safety system for a nuclear reactor includes a first containment structure and a second containment structure. The double containment configuration is designed and configured to meet all design basis accidents and beyond design basis events with independent redundancy. The remaining systems that control reactivity, decay heat removal, and fission product retention may be categorized and designed as business systems, structures, and components, and can therefore be designed and licensed according to an appropriate quality grade for business systems.
A nuclear fuel assembly is constructed with fuel assembly components that are wire wrapped and positioned in hexagonal rings within a fuel assembly duct. The fuel assembly components positioned in an outermost ring of the fuel assembly are wire wrapped with a pitch that is shorter than fuel assembly components positioned at an interior ring of the fuel assembly. The shorter pitch at the outer ring of the fuel assembly increases pressure drop of a coolant fluid at the edge and corner subchannels and thereby reduces the temperature gradient across the fuel assembly, which provides a higher output temperature of the nuclear reactor without substantially increasing peak temperature of the fuel cladding.
A nuclear reactor is configured with an intermediate coolant loop for transferring thermal energy from the reactor core for a useful purpose. The intermediate coolant loop includes a bypass flowpath with an air heat exchanger for dumping reactor heat during startup and/or shutdown. A fluidic diode along the bypass flowpath asymmetrically restricts flow across the bypass flowpath, inhibiting flow in a first flow direction during a full power operating condition and allowing a relatively uninhibited flow in a second direction during a startup and/or shut down low power operating condition.
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
G21C 15/26 - Cyclage du fluide réfrigérant par convection, p. ex. utilisant des cheminées, utilisant des canaux divergents
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
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 curvilinear electromagnetic pump is configured to follow a curve, such as by coupling multiple linear pump segments together that are offset by an angle with respect to each other. The curvilinear electromagnetic pump can curve within two dimensions, or within three dimensions. The curvilinear electromagnetic pump allows for more efficient arrangement of components and systems within a nuclear reactor vessel and allows a significantly reduced reactor vessel height as compared to a linear pump arranged vertically. The curvilinear electromagnetic pump may follow the curvature of the reactor vessel wall and may be entirely disposed near the bottom of the reactor vessel.
G21C 15/247 - Cyclage du fluide réfrigérant pour des liquides pour des métaux liquides
G21C 1/14 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur n'étant pas substantiellement pressurisé, p. ex. réacteur à pile piscine
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
A nuclear reactor includes a heat exchanger that transfers thermal energy from a primary reactor coolant to a secondary coolant. The heat exchanger is a compact plate heat exchanger and more than one heat exchanger may be spaced about the reactor vessel. A plurality of heat exchangers may be spaced vertically, radially, and/or circumferentially about the reactor vessel. A first heat exchanger may be in fluid communication with a second heat exchanger. Two or more heat exchangers may share a thermal load and therefore share thermal stresses. The heat exchanger may have a third fluid flow path and a third fluid. The third fluid may be used to remove fission products, be used for leak detection, create an oxidation layer to inhibit migration of activation products, and/or provide additional heat transfer.
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
F28D 9/00 - Appareils échangeurs de chaleur comportant des ensembles de canalisations fixes en forme de plaques ou de laminés pour les deux sources de potentiel calorifique, ces sources étant en contact chacune avec un côté de la paroi d'une canalisation
81.
DESIGNS FOR FAST SPECTRUM MOLTEN CHLORIDE TEST REACTORS
Alternative designs for a modular test reactor are presented. In one aspect, a molten fuel salt nuclear reactor includes a vessel defining a reactor volume, the vessel being open-topped and otherwise having no penetrations. A neutron reflector is provided within the vessel and displacing at least some of the reactor volume, the neutron reflector defining a reactor core volume. A plurality of heat exchangers are contained within the vessel above the neutron reflector. A flow guide assembly is provided within the neutron reflector that includes a draft tube draft tube separating a central portion of the reactor core volume from an annular downcomer duct. Fuel salt circulates from the reactor core volume, through the heat exchangers, into the downcomer duct and then back into the reactor core volume.
G21C 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
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 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21C 11/06 - Écrans réflecteurs, c.-à-d. pour minimiser la perte de neutrons
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
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 15/22 - Association structurelle des tubes du réfrigérant avec les collecteurs ou autres tuyaux, p. ex. dans des réacteurs à tubes de force
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
A curvilinear electromagnetic pump is configured to follow a curve, such as by coupling multiple linear pump segments together that are offset by an angle with respect to each other. The curvilinear electromagnetic pump can curve within two dimensions, or within three dimensions. The curvilinear electromagnetic pump allows for more efficient arrangement of components and systems within a nuclear reactor vessel and allows a significantly reduced reactor vessel height as compared to a linear pump arranged vertically. The curvilinear electromagnetic pump may follow the curvature of the reactor vessel wall and may be entirely disposed near the bottom of the reactor vessel.
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 1/14 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur n'étant pas substantiellement pressurisé, p. ex. réacteur à pile piscine
G21C 15/247 - Cyclage du fluide réfrigérant pour des liquides pour des métaux liquides
A nuclear reactor includes a heat exchanger that transfers thermal energy from a primary reactor coolant to a secondary coolant. The heat exchanger is a compact plate heat exchanger and more than one heat exchanger may be spaced about the reactor vessel. A plurality of heat exchangers may be spaced vertically, radially, and/or circumferentially about the reactor vessel. A first heat exchanger may be in fluid communication with a second heat exchanger. Two or more heat exchangers may share a thermal load and therefore share thermal stresses. The heat exchanger may have a third fluid flow path and a third fluid. The third fluid may be used to remove fission products, be used for leak detection, create an oxidation layer to inhibit migration of activation products, and/or provide additional heat transfer.
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
84.
CONTAINMENT STRUCTURE AND ARRANGEMENT FOR NUCLEAR REACTOR
A safety system for a nuclear reactor includes a first containment structure and a second containment structure. The double containment configuration is designed and configured to meet all design basis accidents and beyond design basis events with independent redundancy. The remaining systems that control reactivity, decay heat removal, and fission product retention may be categorized and designed as business systems, structures, and components, and can therefore be designed and licensed according to an appropriate quality grade for business systems.
A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
86.
INERTIAL ENERGY COASTDOWN FOR ELECTROMAGNETIC PUMP
A nuclear reactor is configured with a primary coolant loop for transferring heat away from the nuclear reactor core. In a shutdown event, the primary coolant pump may stop pumping primary coolant through the reactor core, resulting in decay heat buildup within the reactor core. An inertial energy coast down system can store kinetic energy while the nuclear reactor is operating and then release the stored kinetic energy to cause the primary coolant to continue to flow through the nuclear reactor core to remove decay heat. The inertial energy coast down system may include an impeller and a flywheel having a mass. During normal reactor operation, the flowing primary coolant spins up the impeller and flywheel, and upon a shutdown event where the primary coolant pump stops pumping, the flywheel and impeller can cause the primary coolant to continue to flow during a coast down of the flywheel and impeller.
G21C 15/247 - Cyclage du fluide réfrigérant pour des liquides pour des métaux liquides
G21C 1/03 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur refroidis par un réfrigérant non nécessairement pressurisé, p. ex. réacteurs du type piscine
G21C 1/14 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur n'étant pas substantiellement pressurisé, p. ex. réacteur à pile piscine
87.
FUEL HANDLING SYSTEM, LAYOUT, AND PROCESS FOR NUCLEAR REACTOR
A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor, an inert gas is applied to the fuel assembly, moisture content in the inert gas is gradually increased as it is applied to the fuel assembly, and the fuel assembly is immersed in water. The fuel assembly is immersed relatively quickly, within about 2 hours or less, which improves safety and allows normal processing and handling equipment to care for the fuel assembly. The fuel assembly may then be loaded into a cask for long-term storage and/or disposal.
G21C 19/08 - Moyens pour le chauffage des éléments combustibles avant leur introduction dans le cœurMoyens pour le chauffage ou le refroidissement des éléments combustibles après leur extraction du cœur
G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles
88.
MODULAR MANUFACTURE, DELIVERY, AND ASSEMBLY OF NUCLEAR REACTOR BUILDING SYSTEMS
A nuclear reactor is constructed in sub-modules and super modules which are manufactured, packaged, and shipped to a construction site. At least some of the modules are packaged in suitable shielding containers or portions of containers, which may be steel. The modules are assembled on-site, and some of the modules remain within their respective shipping containers after assembly. One or more of the shipping containers may be used as concrete forms to support the pouring of concrete in between selected modules. The concrete may be used for structural support, shielding, or both.
A nuclear reactor is designed to allow efficient packing of components within the reactor vessel, such as by offsetting the core, and/or vertically stacking components. The in-vessel storage system can be separate from the support cylinder and these components can be fabricated and shipped separately and coupled together at the construction site. Furthermore, the in-vessel storage system can be located adjacent to the core rather than being located circumferentially around it, and may also be located beneath the heat exchanger to further improve packing of components within the vessel. Through these, and other changes, the delicate components can be manufactured in a manufacturing facility, assembled, and shipped by commercial transportation options without exceeding the shipping envelope.
Alternative designs for a modular test reactor are presented. In one aspect, a molten fuel salt nuclear reactor includes a vessel defining a reactor volume, the vessel being open-topped and otherwise having no penetrations. A neutron reflector is provided within the vessel and displacing at least some of the reactor volume, the neutron reflector defining a reactor core volume. A plurality of heat exchangers are contained within the vessel above the neutron reflector. A flow guide assembly is provided within the neutron reflector that includes a draft tube draft tube separating a central portion of the reactor core volume from an annular downcomer duct. Fuel salt circulates from the reactor core volume, through the heat exchangers, into the downcomer duct and then back into the reactor core volume.
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
G21C 3/54 - Sels fondus, compositions oxydes ou hydroxydes
G21C 11/06 - Écrans réflecteurs, c.-à-d. pour minimiser la perte de neutrons
G21C 15/243 - Cyclage du fluide réfrigérant pour des liquides
A nuclear reactor includes a heat exchanger that transfers thermal energy from a primary reactor coolant to a secondary coolant. The heat exchanger is a compact plate heat exchanger and more than one heat exchanger may be spaced about the reactor vessel. A plurality of heat exchangers may be spaced vertically, radially, and/or circumferentially about the reactor vessel. A first heat exchanger may be in fluid communication with a second heat exchanger. Two or more heat exchangers may share a thermal load and therefore share thermal stresses. The heat exchanger may have a third fluid flow path and a third fluid. The third fluid may be used to remove fission products, be used for leak detection, create an oxidation layer to inhibit migration of activation products, and/or provide additional heat transfer.
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 nuclear fuel assembly is constructed with fuel assembly components that are wire wrapped and positioned in hexagonal rings within a fuel assembly duct. The fuel assembly components positioned in an outermost ring of the fuel assembly are wire wrapped with a pitch that is shorter than fuel assembly components positioned at an interior ring of the fuel assembly. The shorter pitch at the outer ring of the fuel assembly increases pressure drop of a coolant fluid at the edge and corner subchannels and thereby reduces the temperature gradient across the fuel assembly, which provides a higher output temperature of the nuclear reactor without substantially increasing peak temperature of the fuel cladding.
G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 3/16 - Détails de structure à l'intérieur de l'enveloppe
G21C 3/328 - Disposition relative des éléments dans le réseau
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
E04B 1/16 - Structures formées à partir de matériaux en vrac, p. ex. de béton, coulés ou formés de façon analogue, sur place, avec ou sans emploi d'éléments additionnels, tels que coffrages permanents ou infrastructures à recouvrir du matériau porteur de la charge
93.
Reactor core and control elements supported by a reactor vessel head
A nuclear reactor is designed to couple the load path of the control elements with the reactor core, thus reducing the opportunity for differential movement between the control elements and the reactor core. A cartridge core barrel can be fabricated in a manufacturing facility to include the reactor core, control element supports, and control element drive system. The cartridge core barrel can be mounted to a reactor vessel head, and any movement, such as through seismic forces, transmits an equal direction and magnitude to the control elements and the reactor core, thus inhibiting the opportunity for differential movement.
G21C 5/10 - Moyens pour supporter la structure complète
G21C 13/04 - Dispositions pour l'expansion et la contraction
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
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 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 15/247 - Cyclage du fluide réfrigérant pour des liquides pour des métaux liquides
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 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 15/12 - 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
94.
MODULAR MANUFACTURE, DELIVERY, AND ASSEMBLY OF NUCLEAR REACTOR CORE SYSTEMS
A nuclear reactor is designed to allow efficient packing of components within the reactor vessel, such as by offsetting the core, and/or vertically stacking components. The in-vessel storage system can be separate from the support cylinder and these components can be fabricated and shipped separately and coupled together at the construction site. Furthermore, the in-vessel storage system can be located adjacent to the core rather than being located circumferentially around it, and may also be located beneath the heat exchanger to further improve packing of components within the vessel. Through these, and other changes, the delicate components can be manufactured in a manufacturing facility, assembled, and shipped by commercial transportation options without exceeding the shipping envelope.
A nuclear reactor is configured with an intermediate coolant loop for transferring thermal energy from the reactor core for a useful purpose. The intermediate coolant loop includes a bypass flowpath with an air heat exchanger for dumping reactor heat during startup and/or shutdown. A fluidic diode along the bypass flowpath asymmetrically restricts flow across the bypass flowpath, inhibiting flow in a first flow direction during a full power operating condition and allowing a relatively uninhibited flow in a second direction during a startup and/or shut down low power operating condition.
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 5/10 - Moyens pour supporter la structure complète
G21C 13/04 - Dispositions pour l'expansion et la contraction
G21C 13/024 - Structures supportant les cuves de pression ou les enceintes de confinement
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
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 1/02 - Réacteurs de fission rapides, c.-à-d. réacteurs n'utilisant pas de modérateur
G21C 15/247 - Cyclage du fluide réfrigérant pour des liquides pour des métaux liquides
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 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
F16K 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
F16K 15/00 - Soupapes, clapets ou valves de retenue
A curvilinear electromagnetic pump is configured to follow a curve, such as by coupling multiple linear pump segments together that are offset by an angle with respect to each other. The curvilinear electromagnetic pump can curve within two dimensions, or within three dimensions. The curvilinear electromagnetic pump allows for more efficient arrangement of components and systems within a nuclear reactor vessel and allows a significantly reduced reactor vessel height as compared to a linear pump arranged vertically. The curvilinear electromagnetic pump may follow the curvature of the reactor vessel wall and may be entirely disposed near the bottom of the reactor vessel.
F04B 17/03 - Pompes caractérisées par leur combinaison avec des machines motrices ou moteurs particuliers qui les entraînent ou par leur adaptation à ceux-ci entraînées par des moteurs électriques
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 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 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
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
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
97.
Inertial energy coastdown for electromagnetic pump
A nuclear reactor is configured with a primary coolant loop for transferring heat away from the nuclear reactor core. In a shutdown event, the primary coolant pump may stop pumping primary coolant through the reactor core, resulting in decay heat buildup within the reactor core. An inertial energy coast down system can store kinetic energy while the nuclear reactor is operating and then release the stored kinetic energy to cause the primary coolant to continue to flow through the nuclear reactor core to remove decay heat. The inertial energy coast down system may include an impeller and a flywheel having a mass. During normal reactor operation, the flowing primary coolant spins up the impeller and flywheel, and upon a shutdown event where the primary coolant pump stops pumping, the flywheel and impeller can cause the primary coolant to continue to flow during a coast down of the flywheel and impeller.
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
F04B 17/03 - Pompes caractérisées par leur combinaison avec des machines motrices ou moteurs particuliers qui les entraînent ou par leur adaptation à ceux-ci entraînées par des moteurs 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 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 9/00 - Dispositions pour la protection d'urgence structurellement associées avec le réacteur
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
98.
FUEL HANDLING SYSTEM, LAYOUT, AND PROCESS FOR NUCLEAR REACTOR
A method of handling spent nuclear fuel assemblies immerses the spent nuclear fuel assemblies in water in a relatively short time period when compared to traditional methods. A spent nuclear fuel assembly is removed from a nuclear reactor, an inert gas is applied to the fuel assembly, moisture content in the inert gas is gradually increased as it is applied to the fuel assembly, and the fuel assembly is immersed in water. The fuel assembly is immersed relatively quickly, within about 2 hours or less, which improves safety and allows normal processing and handling equipment to care for the fuel assembly. The fuel assembly may then be loaded into a cask for long-term storage and/or disposal.
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21D 1/00 - Détails des installations à énergie nucléaire
G21C 19/07 - Râteliers de stockagePiscines de stockage
G21F 5/008 - Récipients pour éléments combustibles
99.
Modular manufacture, delivery, and assembly of nuclear reactor building systems
A nuclear reactor is constructed in sub-modules and super modules which are manufactured, packaged, and shipped to a construction site. At least some of the modules are packaged in suitable shielding containers or portions of containers, which may be steel. The modules are assembled on-site, and some of the modules remain within their respective shipping containers after assembly. One or more of the shipping containers may be used as concrete forms to support the pouring of concrete in between selected modules. The concrete may be used for structural support, shielding, or both.
G21C 13/10 - Moyens pour prévenir la contamination dans le cas d'une fuite
G21C 15/18 - Dispositions pour le refroidissement d'urgenceMise hors circuit de la chaleur
G21C 3/16 - Détails de structure à l'intérieur de l'enveloppe
G21C 3/328 - Disposition relative des éléments dans le réseau
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
E04B 1/16 - Structures formées à partir de matériaux en vrac, p. ex. de béton, coulés ou formés de façon analogue, sur place, avec ou sans emploi d'éléments additionnels, tels que coffrages permanents ou infrastructures à recouvrir du matériau porteur de la charge
100.
Method, system, and apparatus for the thermal storage of nuclear reactor generated energy
A method, system, and apparatus for the thermal storage of nuclear reactor generated energy including diverting a selected portion of energy from a portion of a nuclear reactor system to an auxiliary thermal reservoir and, responsive to a shutdown event, supplying a portion of the diverted selected portion of energy to an energy conversion system of the nuclear reactor system.
G21D 3/00 - Commande des installations à énergie nucléaire
F01K 3/00 - Ensembles fonctionnels caractérisés par l'emploi d'accumulateurs de vapeur ou de chaleur ou bien de réchauffeurs intermédiaires de vapeur
F01K 3/18 - Ensembles fonctionnels caractérisés par l'emploi d'accumulateurs de vapeur ou de chaleur ou bien de réchauffeurs intermédiaires de vapeur comportant des réchauffeurs
F02C 1/05 - Ensembles fonctionnels de turbines à gaz caractérisés par l'utilisation de gaz chauds ou de gaz sous pression non chauffés, comme fluide de travail le fluide de travail étant chauffé indirectement caractérisés par le type ou la source de chaleur, p. ex. utilisant l'énergie nucléaire ou solaire
G21D 9/00 - Dispositions pour fournir de la chaleur pour des buts autres que la conversion en puissance, p. ex. pour le chauffage des immeubles
F28D 17/00 - Appareils échangeurs de chaleur de régénération dans lesquels un agent ou une masse intermédiaire immobile de transfert de chaleur est mis en contact successivement avec chacune des sources de potentiel calorifique, p. ex. en utilisant des particules granulées
F28D 19/00 - Appareils échangeurs de chaleur de régénération dans lesquels l'agent ou la masse intermédiaire de transfert de chaleur est amené successivement en contact avec chacune des sources de potentiel calorifique
F28D 20/00 - Appareils ou ensembles fonctionnels d'accumulation de chaleur en généralAppareils échangeurs de chaleur de régénération non couverts par les groupes ou
