CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.
B64G 1/40 - Aménagements ou adaptations des systèmes de propulsion
C22C 1/05 - Mélanges de poudre métallique et de poudre non métallique
F02K 7/02 - Ensembles fonctionnels dans lesquels le fluide de travail est utilisé uniquement sous forme de jet, c.-à-d. ensembles ne comportant ni turbine ni autre moteur entraînant un compresseur ou une soufflante carénéeLeur commande le jet étant intermittent, c.-à-d. jet à pulsations
G21C 3/64 - Combustible céramique en dispersion, p. ex. cermet
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21C 5/12 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par la composition, p. ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
2.
NUCLEAR REACTOR FUEL ASSEMBLIES AND PROCESS FOR PRODUCTION
A nuclear fuel assembly for a nuclear reactor core, the fuel assembly having at least one fuel element including an elongated shell defining an interior volume, a lattice structure disposed within the interior volume, at least one flow channel extending through the lattice structure, at least one lattice site disposed in the lattice structure, and at least one fuel compact disposed within a corresponding one of the at least one lattice site, a first end cap including a boss having a first cross-sectional shape, the first end cap being affixed to a first end of the shell, and a second end cap including a first bore having a second cross-sectional shape, the second end cap being affixed to a second end of the shell, wherein the first cross-sectional shape of the boss is the same as the cross-sectional shape of the bore.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21D 5/02 - Réacteur et moteur structurellement combinés, p. ex. portatifs
3.
CARBIDE-BASED FUEL ASSEMBLY FOR THERMAL PROPULSION APPLICATIONS
Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. A continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. Fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
G21C 5/12 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par la composition, p. ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21C 3/64 - Combustible céramique en dispersion, p. ex. cermet
4.
Carbide-based fuel assembly for thermal propulsion applications
Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC—SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a nuclear thermal propulsion reactor.
METHODS OF MANUFACTURING OF MOLYBDENUM AND MOLYBDENUM-BASED STRUCTURES BY ELECTRON BEAM ADDITIVE MANUFACTURING, PARTICULARLY STRUCTURES FOR NUCLEAR COMPONENTS
Methodologies and manufacturing processes to manufacture components by electron beam melting additive manufacturing, particularly components of molybdenum or a molybdenum-based alloy and particularly of complex nuclear component geometries. Input parameters are provided for controlling electron beam melting additive manufacturing equipment, such as electron beam melting machines. The input parameters relate to various process steps, including build set-up, initial thermal treatment, initial layering of powder, pre-consolidation thermal treatment, consolidation, post-consolidation thermal treatment, indexing of layers, and post-build thermal treatment. The methodologies and manufacturing processes allow manufacture of components of molybdenum having a purity of ≥ 99.0% and a density of ≥ 99.75%. Metallographic cross-sections of the manufactured molybdenum components were porosity-free and crack-free.
B29C 64/153 - Procédés de fabrication additive n’utilisant que des matériaux solides utilisant des couches de poudre avec jonction sélective, p. ex. par frittage ou fusion laser sélectif
B22F 10/36 - Commande ou régulation des opérations des paramètres du faisceau d’énergie
B33Y 50/02 - Acquisition ou traitement de données pour la fabrication additive pour la commande ou la régulation de procédés de fabrication additive
H01J 37/305 - Tubes à faisceau électronique ou ionique destinés aux traitements localisés d'objets pour couler, fondre, évaporer ou décaper
6.
METHODS OF MANUFACTURING OF MOLYBDENUM AND MOLYBDENUM-BASED STRUCTURES BY ELECTRON BEAM ADDITIVE MANUFACTURING, PARTICULARLY STRUCTURES FOR NUCLEAR COMPONENTS
Methodologies and manufacturing processes to manufacture components by electron beam melting additive manufacturing, particularly components of molybdenum or a molybdenum-based alloy and particularly of complex nuclear component geometries. Input parameters are provided for controlling electron beam melting additive manufacturing equipment, such as electron beam melting machines. The input parameters relate to various process steps, including build set-up, initial thermal treatment, initial layering of powder, pre-consolidation thermal treatment, consolidation, post-consolidation thermal treatment, indexing of layers, and post-build thermal treatment. The methodologies and manufacturing processes allow manufacture of components of molybdenum having a purity of ≥99.0% and a density of ≥99.75%. Metallographic cross-sections of the manufactured molybdenum components were porosity-free and crack-free.
B23K 15/00 - Soudage ou découpage par faisceau d'électrons
B23K 15/06 - Soudage ou découpage par faisceau d'électrons dans une enceinte sous vide
B23K 37/00 - Dispositifs ou procédés auxiliaires non spécialement adaptés à un procédé couvert par un seul des autres groupes principaux de la présente sous-classe
G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
An aft plenum assembly for use with a nuclear thermal reactor including a pressure vessel and a nozzle assembly having a top plenum plate disposed within the pressure vessel, the top plenum plate defining a first plurality of fuel flow apertures, a bottom plenum plate disposed within the pressure vessel, the bottom plenum plate being parallel to the top plenum plate thereby defining a plenum space therebetween, the bottom plenum plate defining a second plurality of fuel flow apertures, and a plurality of tubular connections extending between the first plurality of fuel flow apertures of the top plenum plate and the second plurality of fuel flow apertures of the bottom plenum plate, wherein the aft plenum assembly is disposed between the pressure vessel and the nozzle assembly.
G21C 15/253 - Cyclage du fluide réfrigérant pour des gaz, p. ex. ventilateurs
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
G21D 5/02 - Réacteur et moteur structurellement combinés, p. ex. portatifs
8.
CARBIDE-BASED FUEL ASSEMBLY FOR THERMAL PROPULSION APPLICATIONS
Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. A continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. A fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and has the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a NTP reactor.
B64G 1/40 - Aménagements ou adaptations des systèmes de propulsion
B64G 1/42 - Aménagements ou adaptations des systèmes fournissant l'énergie
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
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
9.
CERMET FUEL ELEMENT AND FABRICATION AND APPLICATIONS THEREOF, INCLUDING IN THERMAL PROPULSION REACTOR
CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.
Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC-SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a NTP reactor.
G21D 5/02 - Réacteur et moteur structurellement combinés, p. ex. portatifs
G21C 11/08 - Écrans thermiquesRevêtements thermiques, c.-à-d. pour dissiper la chaleur provenant de radiations gamma qui sans cela chaufferaient un écran biologique externe
G21C 3/22 - Éléments combustibles avec un matériau fissile ou surrégénérateur en contact avec le réfrigérant
G21C 3/42 - Emploi de substances spécifiées comme combustibles pour réacteurs
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material, the interior surface of which is lined in higher temperature regions with an insulation layer of porous refractory ceramic material. Continuous insulation layer extends the length of the fuel assembly or separate insulation layer sections have a thickness increasing step-wise along the length of the fuel assembly from upper (inlet) section towards bottom (outlet) section. A fuel element positioned inward of the insulation layer and between support meshes has a fuel composition including HALEU and the form of a plurality of individual elongated fuel bodies or one or more fuel monolith bodies containing coolant flow channels. Fuel assemblies are distributively arranged in a moderator block, with upper end of the outer structural member attached to an inlet for propellant and lower end of the outer structural member operatively interfaced with a nozzle forming a nuclear thermal propulsion reactor.
G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
G21C 5/12 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par la composition, p. ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21C 3/64 - Combustible céramique en dispersion, p. ex. cermet
F02K 9/42 - Moteurs-fusées, c.-à-d. ensembles fonctionnels portant à la fois le combustible et son oxydantLeur commande utilisant des propergols liquides ou gazeux
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
B64G 1/40 - Aménagements ou adaptations des systèmes de propulsion
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 3/324 - Chemisages ou enveloppes pour les faisceaux
12.
Cermet fuel element and fabrication and applications thereof, including in thermal propulsion reactor
CERMET fuel element includes a fuel meat of consolidated ceramic fuel particles (preferably refractory-metal coated HALEU fuel kernels) and an array of axially-oriented coolant flow channels. Formation and lateral positions of coolant flow channels in the fuel meat are controlled during manufacturing by spacer structures that include ceramic fuel particles. In one embodiment, a coating on a sacrificial rod (the rod being subsequently removed) forms the coolant channel and the spacer structures are affixed to the coating; in a second embodiment, a metal tube forms the coolant channel and the spacer structures are affixed to the metal tube. The spacer structures laterally position the coolant channels in spaced-apart relation and are consolidated with the ceramic fuel particles to form CERMET fuel meat of a fuel element, which are subsequently incorporated into fuel assemblies that are distributively arranged in a moderator block within a nuclear fission reactor, in particular for propulsion.
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
G21C 3/64 - Combustible céramique en dispersion, p. ex. cermet
G21C 5/12 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par la composition, p. ex. le modérateur contenant des substances additionnelles qui assurent une meilleure résistance du modérateur
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
C22C 1/05 - Mélanges de poudre métallique et de poudre non métallique
B64G 1/40 - Aménagements ou adaptations des systèmes de propulsion
F02K 7/02 - Ensembles fonctionnels dans lesquels le fluide de travail est utilisé uniquement sous forme de jet, c.-à-d. ensembles ne comportant ni turbine ni autre moteur entraînant un compresseur ou une soufflante carénéeLeur commande le jet étant intermittent, c.-à-d. jet à pulsations
13.
Carbide-based fuel assembly for thermal propulsion applications
Carbide-based fuel assembly includes outer structural member of ceramic matrix composite material (e.g., SiC—SiC composite), insulation layer of porous refractory ceramic material (e.g., zirconium carbide with open-cell foam structure or fibrous zirconium carbide), and interior structural member of refractory ceramic-graphite composite material (e.g., zirconium carbide-graphite or niobium carbide-graphite). Spacer structures between various layers provide a defined and controlled spacing relationship. A fuel element bundle positioned between support meshes includes a plurality of distributively arranged fuel elements or a solid, unitary fuel element with coolant channels, each having a fuel composition including high assay, low enriched uranium (HALEU). Fuel assemblies are distributively arranged in a moderator block and the upper end of the outer structural member is attached to a metallic inlet tube for hydrogen propellant and the lower end of the outer structural member is interfaced with a support plate, forming a nuclear thermal propulsion reactor.
Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21C 5/14 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par la forme
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant des éléments combustibles de différentes compositionsFaisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p. ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 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
B33Y 80/00 - Produits obtenus par fabrication additive
B33Y 50/00 - Acquisition ou traitement de données pour la fabrication additive
15.
Nuclear reactor fuel assemblies and process for production
A nuclear fuel assembly for a nuclear reactor core, the fuel assembly having at least one fuel element including an elongated shell defining an interior volume, a lattice structure disposed within the interior volume, at least one flow channel extending through the lattice structure, at least one lattice site disposed in the lattice structure, and at least one fuel compact disposed within a corresponding one of the at least one lattice site, a first end cap including a boss having a first cross-sectional shape, the first end cap being affixed to a first end of the shell, and a second end cap including a first bore having a second cross-sectional shape, the second end cap being affixed to a second end of the shell, wherein the first cross-sectional shape of the boss is the same as the cross-sectional shape of the bore.
G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21D 5/02 - Réacteur et moteur structurellement combinés, p. ex. portatifs
16.
NUCLEAR REACTOR FUEL ASSEMBLIES AND PROCESS FOR PRODUCTION
A nuclear fuel assembly for a nuclear reactor core, the fuel assembly having at least one fuel element including an elongated shell defining an interior volume, a lattice structure disposed within the interior volume, at least one flow channel extending through the lattice structure, at least one lattice site disposed in the lattice structure, and at least one fuel compact disposed within a corresponding one of the at least one lattice site, a first end cap including a boss having a first cross-sectional shape, the first end cap being affixed to a first end of the shell, and a second end cap including a first bore having a second cross-sectional shape, the second end cap being affixed to a second end of the shell, wherein the first cross-sectional shape of the boss is the same as the cross-sectional shape of the bore.
A nuclear reactor has first and second plenum plates disposed in a pressure vessel. Both plenum plates have a plurality of apertures. The second plenum plate is parallel to the first plenum plate. A fuel element includes a fuel element coolant flow tube which extends through aligned apertures of the parallel plenum plates. A fuel element standoff spool is disposed about a portion of the fuel element coolant flow tube which is located between the plenum plates. The nuclear reactor is also usable in nuclear thermal propulsion.
A nuclear reactor having a pressure vessel, the reactor including a first plenum plate disposed within the pressure vessel, the first plenum plate defining a first plurality of apertures, a second plenum plate disposed within the pressure vessel, the second plenum plate being parallel to the first plenum plate and defining a first plurality of apertures, a fuel element including a fuel element flow tube extending through a first one of both the first pluralities of apertures of both the first and the second plenum plates, and a first fuel element standoff spool being disposed about a portion of the fuel element flow tube that is disposed between the first and the second plenum plates.
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 1/08 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés le modérateur étant hautement pressurisé, p. ex. réacteur à eau bouillante, réacteur à surchauffe intégrale, réacteur à eau pressurisée
G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
An internal interface structure of a nuclear thermal propulsion nuclear reactor including a reactor vessel and a reactor head, including a substantially cylindrical body having a top end, a bottom end, an inner surface, and an outer surface, and an annular flange extending radially-outwardly from the outer surface of the body, wherein the annular flange of the interface structure is mounted between an upper flange of the reactor vessel and a bottom flange of the reactor head.
An internal interface structure of a nuclear thermal propulsion nuclear reactor including a reactor vessel and a reactor head, including a substantially cylindrical body having a top end, a bottom end, an inner surface, and an outer surface, and an annular flange extending radially- outwardly from the outer surface of the body, wherein the annular flange of the interface structure is mounted between an upper flange of the reactor vessel and a bottom flange of the reactor head.
G21C 1/22 - Réacteurs hétérogènes, c.-à-d. dans lesquels le combustible et le modérateur sont séparés utilisant du combustible liquide ou gazeux
G21C 1/32 - Réacteurs du type intégré, c.-à-d. réacteurs dans lesquels des parties associées de façon fonctionnelle avec le réacteur, mais non essentielles à la réaction, p. ex. des échangeurs de chaleur, sont disposées à l'intérieur de l'enveloppe avec le cœur
G21C 1/09 - Dispositions pour la régulation de pression, c.-à-d. pressuriseurs
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
21.
Apparatus for desuperheating high temperature, high velocity steam
A desuperheating spray chamber for use in a rocket exhaust recovery system for a nuclear thermal propulsion rocket, including a substantially-cylindrical outer tank with an upper end including an entrance port and two exhaust ports, a substantially-cylindrical shroud extending downwardly from an inner surface of the upper end of the tank, an annular inner spray ring that is both disposed within and concentric with the shroud; and an annular outer spray ring that is disposed between a side wall of the outer tank and the shroud, the annular outer ring being concentric with the shroud.
A desuperheating spray chamber for use in a rocket exhaust recovery system for a nuclear thermal propulsion rocket, including a substantially-cylindrical outer tank with an upper end including an entrance port and two exhaust ports, a substantially-cylindrical shroud extending downwardly from an inner surface of the upper end of the tank, an annular inner spray ring that is both disposed within and concentric with the shroud; and an annular outer spray ring that is disposed between a side wall of the outer tank and the shroud, the annular outer ring being concentric with the shroud.
A packing device for filling fuel elements with a powder through a fill aperture in an outer shell of the fuel element, including a stationary base, a clamp assembly including a body defining a bore therein, the bore being configured to slidably receive a fuel element therein, wherein the clamp assembly is movable along a vertical axis with respect to the stationary base, a cam assembly including a cam and a drive motor configured to rotate the cam, wherein rotation of the cam alternatingly raises the clamp assembly up along the vertical axis and subsequently drops the clamping assembly, and a powder reservoir assembly including a powder reservoir and a fill needle in fluid communication with the powder reservoir.
A packing device for filling fuel elements with a powder through a fill aperture in an outer shell of the fuel element, including a stationary base, a clamp assembly including a body defining a bore therein, the bore being configured to slidably receive a fuel element therein, wherein the clamp assembly is movable along a vertical axis with respect to the stationary base, a cam assembly including a cam and a drive motor configured to rotate the cam, wherein rotation of the cam alternatingly raises the clamp assembly up along the vertical axis and subsequently drops the clamping assembly, and a powder reservoir assembly including a powder reservoir and a fill needle in fluid communication with the powder reservoir.
Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.
G21C 5/02 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur Détails
G21C 5/14 - Structure du modérateur ou du cœurEmploi de matériaux spécifiés comme modérateur caractérisée par la forme
G21C 3/326 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant des éléments combustibles de différentes compositionsFaisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles comprenant, en plus des éléments combustibles, d'autres éléments en forme d'aiguille, de barre ou de tube, p. ex. barres de commande, barres de support de grilles, barres fertiles, barres à poison ou barres factices
G21C 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
B33Y 80/00 - Produits obtenus par fabrication additive
B33Y 50/00 - Acquisition ou traitement de données pour la fabrication additive
G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
26.
UNIVERSAL INVERTED REACTOR AND METHOD FOR DESIGN AND MANUFACTURE OF UNIVERSAL INVERTED REACTOR
Fission reactor has a shell encompassing a reactor space within which are a central longitudinal channel, a plurality of axially extending rings with adjacent rings defining an annular cylindrical space in which a first plurality of primary axial tubes are circumferential located. Circumferentially adjacent primary axial tubes are separated by one of the plurality of secondary channels and a plurality of webbings connects at least a portion of the plurality of primary axial tubes to adjacent structure. A fissionable nuclear fuel composition is located in at least some of the plurality of secondary channels and a primary coolant passes thorough at least some of the primary axial tubes. Additive and/or subtractive manufacturing techniques produce an integral and unitary structure for the fuel loaded reactor space. During manufacturing and as-built, the reactor design can be analyzed using a computational platform that integrates and analyzes data from in-situ monitoring during manufacturing.
G21C 13/02 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général Détails
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 15/02 - 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 15/04 - 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 3/40 - Combinaison structurelle d'un élément combustible avec un élément thermo-électrique pour la production directe d'énergie électrique à partir de la chaleur de fission
A nuclear reactor includes a pressure vessel, and a control rod assembly (CRA) including at least one movable control rod, a control rod drive mechanism (CRDM) for controlling movement of the at least one control rod, and a coupling operatively connecting the at least one control rod and the CRDM. The coupling includes a connecting rod engaged with the CRDM and a terminal element connected with a lower end of the connecting rod and further connected with the at least one control rod. In some embodiments the terminal element includes a first portion comprising a first material having a first density and a second portion comprising a second material having a second density that is greater than the first density. In some embodiments the terminal element has a largest dimension parallel with the connecting rod that is greater than or equal to a largest dimension transverse to the connecting rod.
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