Abrégé

The present invention relates to a method for producing a nuclear design core model accounting for load following, the method comprising the steps of: receiving load-following requirements for a corresponding cycle, wherein the load-following requirements include the amount of power reduction, the number of load-following operations, and at least one of the time or duration of operation at reduced power; determining the amount of insertion of a control rod on the basis of the load-following requirements; determining the duration of insertion of the control rod on the basis of the amount of insertion of the control rod and the maximum insertion limit thereof; determining the time of insertion of the control rod by simulating core combustion by reflecting the duration of insertion of the control rod in a nuclear design code at each of a plurality of time points of the corresponding cycle; and producing a nuclear design core model accounting for load following on the basis of the determined amount of insertion of the control rod, the determined duration of insertion of the control rod, and the determined time of insertion of the control rod.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• 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
• G06F 30/20 - Optimisation, vérification ou simulation de l’objet conçu

Abrégé

The present invention relates to a spot-welding jig used to spot-weld a spacer grid of a nuclear fuel assembly, the spot-welding jig comprising: a base plate (110); a guide member (120) provided in parallel on the upper surface of the base plate (110); a movable plate (130) provided on the base plate (110) in a way that allows left-and-right movement by the guide member (120); a pair of spacer grid fixing parts (131) provided on the movable plate (130) to support the two end portions of a spacer grid (10); horizontal adjustment parts (140) provided on the base plate (110) to adjust the horizontal (x-axis) position of the movable plate (130); and a vertical adjustment part (150) provided on the base plate (110) to adjust the vertical (y-axis) position of the spacer grid seated on the movable plate (130).

Classes IPC  ?

• G21C 3/34 - Grilles d'espacement

Abrégé

Proposed is a device for assembling and disassembling a top nozzle of a nuclear fuel assembly wherein the top nozzle of the nuclear fuel assembly is assembled and disassembled with improved convenience, and the load value is measured to ensure stable operations without damaging components. To this end, the device includes a pedestal including a threaded hole through both sides, a screw bar screw-coupled to the threaded hole to reciprocate in a straight line, a top nozzle plate configured to be detachably coupled to the screw bar and to be able to be hooked by and coupled to the top nozzle of the nuclear fuel assembly, and a load cell provided between the top nozzle plate and the screw bar to measure a load value applied to the top nozzle plate hooked on the top nozzle.

Classes IPC  ?

• G21C 3/334 - Assemblage des faisceaux
• 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

Abrégé

Proposed is a method of synthesizing reactor core power distribution using an in-core instrument in a reactor core protection system, that is, a method of synthesizing reactor core power distribution for a reactor core protection system based on an in-core instrument signal using an ordinary kriging method. According to the present disclosure, a power of all fuel assemblies in a reactor core is calculated from powers of fuel assemblies where in-core instruments are located using the ordinary kriging methodology, and a hot-pin power distribution of each fuel assembly is synthesized from the power of all fuel assemblies calculated, whereby there is an effect that more accurate hot-pin axial power distribution, rather than pseudo hot-pin axial power distribution, may be synthesized.

Classes IPC  ?

• G21C 17/108 - Mesure du flux

Abrégé

The present invention relates to an ultrasonic apparatus for decontaminating solid radioactive waste contaminated by radiation. The ultrasound apparatus for decontaminating solid radioactive waste includes: a container having a cylindrical shape; and a plurality of ultrasonic generators attached to an outer surface of a lower portion of the container and apart from each other at predetermined intervals, wherein in a state in which the container is filled with water, and the ultrasound apparatus decontaminates the solid radioactive waste by using ultrasonic waves generated from the plurality of ultrasonic generators, wherein the lower portion of the container has a downwardly-convex hemispherical shape, and the plurality of ultrasonic generators are attached to the hemispherical lower portion of the container such that ultrasonic waves generated from the plurality of ultrasonic generators may be focused on one point in the container.

Classes IPC  ?

• G21F 9/30 - Traitements
• B09B 3/30 - Destruction de déchets solides ou transformation de déchets solides en quelque chose d'utile ou d'inoffensif impliquant un traitement mécanique

Produits et services

Fuel for nuclear reactors; fissionable material for nuclear energy

Produits et services

Fuel for nuclear reactors; fissionable material for nuclear energy.

Abrégé

A method for preparing a UO2 mixture powder for nuclear fuel manufacturing, comprises the steps of: (a) weighing and sieving, by means of an automatic injection device, a UO2 powder, a porogen and a lubricant, and injecting same into a UC container; and (b) mixing the UO2 powder, the porogen and the lubricant by means of an IBC blender. According to a method for preparing a UO2 mixture powder for nuclear fuel manufacturing, mixing time is short, and degrees of mixing and homogeneity of a prepared UO2 mixture powder are excellent.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• G21C 3/04 - Détails de structure
• G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci

Abrégé

The present invention relates to a transport container for a fresh nuclear fuel assembly for a light-water reactor, the transport container including: a lower housing (100) having a semi-cylindrical shape; an upper housing (200) having a semi-cylindrical shape and assembled to the upper part of the lower housing (100); a base frame (110) provided to horizontally extend in the longitudinal direction of the lower housing (100), provided with a partition (111) vertically formed at the center thereof, and allowing a pair of nuclear fuel assemblies to be seated thereon with reference to the partition (111); a pair of covers (120) rotatably provided at the opposite ends of the base frame (110), respectively, to cover the nuclear fuel assemblies seated on the base frame (110); and a neutron absorption plate (130) fixed to each of nuclear fuel assembly seat surfaces of the base frame (110) so as to absorb neutrons.

Classes IPC  ?

• G21F 5/015 - Récipients blindés portatifs ou transportables pour le stockage de sources radioactives, p. ex. supports de sources pour unités d'irradiationRécipients pour radio-isotopes
• 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

Abrégé

The present invention relates to a method for synthesizing the power distribution of a nuclear reactor core in a core protection system by using an in-reactor measuring instrument, and relates to a method for synthesizing the power distribution of a nuclear reactor core using the ordinary kriging method, wherein the method is based on an in-reactor measuring instrument signal. According to the present invention, the power of all assemblies in a core are calculated from the power of an assembly in which the in-reactor measuring instrument is located by using the ordinary kriging method, and the hot rod power distributions of the respective assemblies are synthesized from the calculated power of the assemblies, thus having the effect of making it possible to synthesize a more accurate assembly hot rod power distribution rather than a virtual hot rod power distribution.

Classes IPC  ?

• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes

Abrégé

The present invention relates to equipment for assembling and disassembling a top retainer of a nuclear fuel assembly and, more specifically, to equipment for assembling and disassembling a top retainer of a nuclear fuel assembly, wherein the top retainer of the nuclear fuel assembly can be assembled and disassembled with improved convenience, and the load value applied to a top nozzle plate when the top retainer is assembled and disassembled can be measured, thereby ensuring stable operations without damaging components. To this end, the present invention provides equipment for assembling and disassembling a top retainer of a nuclear fuel assembly, the equipment comprising: a support table including a screw hole, both sides of which penetrate same; a screw bar screw-coupled to the screw hole and installed to be able to linearly reciprocate through screw rotation; a top nozzle plate detachably coupled to the screw bar and provided such that same can engage with and coupled to the top retainer of the nuclear fuel assembly; and a load cell installed between the top nozzle plate and the screw bar and provided to be able to measure a load value applied to the top nozzle plate that has engaged with the top retainer.

Classes IPC  ?

• 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

Abrégé

Proposed is an internal electrode insertion device for transferring the internal electrode to a welding position in order to weld a skeleton of a nuclear fuel assembly, the device including: a table; a plurality of internal electrode bars disposed in parallel in a plurality of rows on a top portion of the table; guide members provided on the table and configured to guide a horizontal movement of the internal electrode bars; guide rails provided in parallel with an alignment direction of the internal electrode bars on the top portion of the table; a driving unit provided with a servomotor thereon, thereby performing horizontal movement driving along the guide rails; and a control unit for controlling driving of the servomotor based on a preset position of each of the internal electrodes.

Classes IPC  ?

• G21C 3/334 - Assemblage des faisceaux
• G21C 3/34 - Grilles d'espacement

Abrégé

Proposed is a spacer grid of a nuclear fuel assembly that may be manufactured using 3D printing with a high degree of design freedom, excluding sheet metal processing and welding processing. The spacer grid of the nuclear fuel assembly has hollow grid cells (110) having inner walls (111) arranged in a square lattice structure and connected to each other by being circumscribed, each of the grid cells including: a plurality of elastic support portions (112) protrudingly provided by being curved inwardly from the inner walls (111) and elastically supporting a fuel rod (10) in a state in which at least three elastic support portions are disposed at equal angles; and a plurality of inner mixing vanes (113) protrudingly provided while each upper tip portion thereof spirally turns along an associated one of the inner walls above the elastic support portions (112).

Classes IPC  ?

• G21C 3/356 - Grilles d'espacement munies d'organes de support des éléments combustibles
• G21C 3/344 - Grilles d'espacement formées par un assemblage d'éléments tubulaires
• G21C 3/34 - Grilles d'espacement

Abrégé

2222222 powder, the porogen and the lubricant by means of an IBC blender.

Classes IPC  ?

• G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
• G21C 3/62 - Combustible céramique
• G21C 3/04 - Détails de structure

Abrégé

The present invention relates to an apparatus for decontaminating solid radioactive waste which has been radioactively contaminated. An ultrasound apparatus for decontaminating solid radioactive waste comprises: a cylindrical vessel having an open upper portion; and a plurality of ultrasonic generators attached to the outer surface of the lower portion of the vessel so as to be spaced from each other at predetermined intervals, wherein, in a state where water is filled in the vessel, solid radioactive waste is placed in the water, and decontamination thereof is carried out by means of ultrasonic waves generated from the plurality of ultrasonic generators, and the lower portion of the vessel is hemispherically shaped so as to be downwardly convex, and the ultrasonic generators are attached to the hemispherical lower portion of the vessel so as to enable the ultrasonic waves generated from the plurality of ultrasonic generators to be focused at one point in the vessel.

Classes IPC  ?

• B06B 1/02 - Procédés ou appareils pour produire des vibrations mécaniques de fréquence infrasonore, sonore ou ultrasonore utilisant l'énergie électrique
• G21F 9/00 - Traitement des matériaux contaminés par la radioactivitéDispositions à cet effet pour la décontamination
• G21F 9/30 - Traitements

Abrégé

The present invention relates to an apparatus for decontaminating solid radioactive waste which has been radioactively contaminated. An ultrasound apparatus for decontaminating solid radioactive waste comprises: a cylindrical vessel having an open upper portion; and a plurality of ultrasonic generators attached to the outer surface of the lower portion of the vessel so as to be spaced from each other at predetermined intervals, wherein, in a state where water is filled in the vessel, solid radioactive waste is placed in the water, and decontamination thereof is carried out by means of ultrasonic waves generated from the plurality of ultrasonic generators, and the lower portion of the vessel is hemispherically shaped so as to be downwardly convex, and the ultrasonic generators are attached to the hemispherical lower portion of the vessel so as to enable the ultrasonic waves generated from the plurality of ultrasonic generators to be focused at one point in the vessel.

Classes IPC  ?

• G21F 9/30 - Traitements
• G21F 9/00 - Traitement des matériaux contaminés par la radioactivitéDispositions à cet effet pour la décontamination
• B06B 1/02 - Procédés ou appareils pour produire des vibrations mécaniques de fréquence infrasonore, sonore ou ultrasonore utilisant l'énergie électrique

Abrégé

A light-water reactor nuclear fuel rod loading apparatus, which comprises a spacer grid holder and a loading power device installed with a traction module configured to reciprocally move toward the spacer grid holder. The loading apparatus further comprises a hollow cladding tube sample and a pulling bar comprising one end part and an opposite end part. The one end part passing in use through a cell of a spacer grid held by the spacer grid holder and configured to couple to the hollow cladding tube sample. The opposite end part is coupled to the traction module. The loading apparatus further comprises: a measuring device installed on the pulling bar and configured to measure loading force of the traction module loading the pulling bar; a holder cap; and a holder comprising an end part configured to in use pass through the cladding tube sample and couple to the holder cap.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• G21C 3/334 - Assemblage des faisceaux

Abrégé

Proposed are nuclear fuel pellets showing high oxidation resistance in a steam atmosphere and a method for manufacturing same. The method includes: preparing a powder mixture by mixing a sintering additive powder including Cr2O3, MnO, and SiO2 with a uranium dioxide powder; forming a molded body by subjecting the powder mixture to compression molding; and sintering the molded body in a weak oxidative atmosphere in which an oxygen potential is −581.9 kJ/mol to −218.2 kJ/mol. The nuclear fuel pellets contain 0.05% to 0.16% by weight of the sintering additive composed of Cr2O3, MnO, and SiO2. A liquid phase generated during the sintering accelerates grain growth and inhibits reaction between uranium dioxide with steam by forming a film at the grain boundary of the uranium dioxide. This reduces leakage of a fission material by improving high-temperature water vapor oxidation resistance at around 1204° C. in a loss-of-coolant accident condition.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• C04B 35/51 - Produits céramiques mis en forme, caractérisés par leur compositionCompositions céramiquesTraitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base de composés des actinides
• C04B 35/63 - Préparation ou traitement des poudres individuellement ou par fournées utilisant des additifs spécialement adaptés à la formation des produits
• C04B 35/645 - Frittage sous pression

Abrégé

A device for supplementing structural integrity of a spent nuclear fuel assembly during handling is provided. The spent nuclear fuel assembly includes spacer grids for supporting fuel rods, guide tubes, and top and bottom nozzles for supporting upper and lower ends of the guide tubes. The device includes a housing, a rod member and fixing members. The housing includes a plurality of free end portions, stopper protrusions formed at an end of each of the free end portions, a first male thread formed on an outer surface, and a female thread formed on an inner surface. The rod member includes a pressurization protrusion at one end and a second male thread for engaging with the female thread of the housing. The fixing members are configured engage with the first male thread to secure the device to the top nozzle of the spent nuclear fuel assembly.

Classes IPC  ?

• G21C 19/20 - Dispositions pour introduire des objets à l'intérieur de l'enceinte sous pressionDispositions pour manipuler des objets à l'intérieur de l'enceinte sous pressionDispositions pour extraire des objets de l'enceinte sous pression
• G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
• G21C 19/19 - Parties de réacteurs spécifiquement adaptées pour faciliter la manipulation, p. ex. pour faciliter le chargement ou le déchargement des éléments combustibles

Abrégé

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.

Classes IPC  ?

• G21F 9/16 - Traitements par fixation dans un milieu solide stable
• C04B 14/36 - Matières inorganiques non prévues par les groupes
• C04B 28/06 - Ciments alumineux
• G21F 9/34 - Moyens de se débarrasser des résidus solides
• C04B 22/14 - Acides ou leurs sels comportant du soufre dans la partie anionique, p. ex. sulfures

Abrégé

The present invention relates to an internal electrode insertion device for automatically transferring multiple internal electrodes to a welding position in welding equipment for the skeleton of a nuclear fuel assembly and, more specifically, to an internal electrode insertion device for transferring internal electrodes to a welding position in order to weld the skeleton of a nuclear fuel assembly. The internal electrode insertion device comprises: a table (110); multiple internal electrode bars (120) including internal electrodes (121a) (121b) and arranged parallel to each other in multiple rows above the table (110); a guide member (130) provided at the table (110) so as to guide the horizontal movement of the internal electrode bars (120); guide rails (140) arranged on the table (110) in a direction parallel to the direction of alignment of the internal electrode bars (120); a driving unit (150) to which the rear ends of the internal electrode bars (120) are fixed and which includes a servo motor (151) horizontally driven along the guide rails (140); and a control unit (200) for controlling driving of the servo motor (151) such that positions of the internal electrodes, predetermined according to input types of fuel for the nuclear fuel assembly, are reflected in the driving.

Classes IPC  ?

• B23K 11/31 - Porte-électrodes
• G21C 3/334 - Assemblage des faisceaux
• G21C 3/34 - Grilles d'espacement
• G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci

Abrégé

The present invention relates to a method, for treating uranium carbide (UCx) scraps, comprising: a step (a) of inputting uranium carbide scraps, which are produced during a process of preparing uranium carbide (UCx-C) from uranium oxide, in a dedicated crucible and inputting same to a heat treatment furnace; a heat-treating step (b) of sublimating carbon in the uranium carbide scraps by temporally raising the temperature in accordance with a heat treatment condition of the heat treatment furnace; and a step (c) of recovering uranium oxide which is produced by removing the carbon from the uranium carbide scraps by performing the step (b). Therefore, the uranium carbide scraps are treated such that the recovered uranium oxide can be reused.

Classes IPC  ?

• C01G 43/01 - OxydesHydroxydes
• G21F 9/32 - Traitements par incinération

Abrégé

The present invention relates to a method, for treating uranium carbide (UCx) scraps, comprising: a step (a) of inputting uranium carbide scraps, which are produced during a process of preparing uranium carbide (UCx-C) from uranium oxide, in a dedicated crucible and inputting same to a heat treatment furnace; a heat-treating step (b) of sublimating carbon in the uranium carbide scraps by temporally raising the temperature in accordance with a heat treatment condition of the heat treatment furnace; and a step (c) of recovering uranium oxide which is produced by removing the carbon from the uranium carbide scraps by performing the step (b). Therefore, the uranium carbide scraps are treated such that the recovered uranium oxide can be reused.

Classes IPC  ?

• G21F 9/32 - Traitements par incinération
• G21F 9/34 - Moyens de se débarrasser des résidus solides
• C01G 43/01 - OxydesHydroxydes

Abrégé

m; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• C04B 35/626 - Préparation ou traitement des poudres individuellement ou par fournées
• C04B 35/628 - Revêtement des poudres
• C04B 35/634 - Polymères
• C04B 35/565 - Produits céramiques mis en forme, caractérisés par leur compositionCompositions céramiquesTraitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base de non oxydes à base de carbures à base de carbure de silicium
• C04B 35/632 - Additifs organiques
• C04B 35/645 - Frittage sous pression
• C04B 38/00 - Mortiers, béton, pierre artificielle ou articles de céramiques poreuxLeur préparation
• 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 21/04 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par compactage ou pilonnage par vibration

Abrégé

2 sintering additive is added to uranium dioxide so that mass movement is accelerated due to the liquid phase generated during sintering of the uranium-dioxide pellet, which promotes the growth of grains thereof. Further, since less volatilization occurs during sintering due to the low vapor pressure of the liquid phase, efficient additive performance is exhibited, so the liquid phase surrounding the grain boundary effectively adsorbs cesium, which is a nuclear fission gas.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• G21C 3/04 - Détails de structure
• G21C 21/18 - Fabrication des éléments de commande couverts par le groupe

Abrégé

m; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• C04B 35/626 - Préparation ou traitement des poudres individuellement ou par fournées
• C04B 35/628 - Revêtement des poudres
• C04B 35/634 - Polymères
• C04B 35/565 - Produits céramiques mis en forme, caractérisés par leur compositionCompositions céramiquesTraitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base de non oxydes à base de carbures à base de carbure de silicium
• C04B 35/632 - Additifs organiques
• C04B 35/645 - Frittage sous pression
• C04B 38/00 - Mortiers, béton, pierre artificielle ou articles de céramiques poreuxLeur préparation
• 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 21/04 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par compactage ou pilonnage par vibration

Abrégé

6 gas leak. Further, the system extends the mechanical life of and reduces the maintenance and repair costs for the detection apparatus.

Classes IPC  ?

• G21C 17/00 - SurveillanceTests
• G01M 3/20 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des révélateurs particuliers, p. ex. teinture, produits fluorescents, produits radioactifs
• G01M 3/38 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation de la lumière
• G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
• C01G 43/06 - Fluorures

Abrégé

Disclosed is a composition of a lubricant for cold pilgering of zirconium alloy tubes. More particularly, disclosed is a composition of an external lubricant for cold pilgering of a zirconium alloy cladding tube, the composition exhibiting excellent lubricity and decomposition against microbes.

Classes IPC  ?

• C10M 173/00 - Compositions lubrifiantes contenant plus de 10% d'eau
• C10M 101/02 - Fractions de pétrole
• C10M 125/10 - Oxydes, hydroxydes, carbonates, bicarbonates, métalliques
• C10M 127/02 - Compositions lubrifiantes caractérisées en ce que l'additif est un hydrocarbure non macromoléculaire aliphatique défini
• C10M 129/08 - Composés hydroxylés comportant des groupes hydroxyle liés à des atomes de carbone acycliques ou cycloaliphatiques contenant au moins 2 groupes hydroxyle
• C10M 135/10 - Acides sulfoniques ou leurs dérivés
• C10M 135/36 - Composés hétérocycliques contenant du soufre, du sélénium ou du tellure le cycle contenant du soufre et du carbone ainsi que de l'azote ou de l'oxygène
• C10M 141/08 - Compositions lubrifiantes caractérisées en ce que l'additif est un mélange d'au moins deux composés couverts par plus d'un des groupes principaux , chacun de ces composés étant un composé essentiel l'un d'eux, au moins, étant un composé organique contenant du soufre, du sélénium ou du tellure
• C10M 169/04 - Mélanges de matériaux de base et d'additifs
• C10N 40/20 - Travail des métaux
• C10N 30/06 - OnctuositéRésistance du filmAnti-usureRésistance aux pressions extrêmes
• C10N 40/24 - Travail des métaux sans enlèvement substantiel de matièreDécoupage du métal à l'emporte-pièce

Abrégé

Disclosed is a composition of a lubricant for cold pilgering of zirconium alloy tubes. More particularly, disclosed is a composition of an internal lubricant for cold pilgering of a zirconium alloy cladding tube, the composition exhibiting excellent lubricity and decomposition against microbes.

Classes IPC  ?

• C10M 169/04 - Mélanges de matériaux de base et d'additifs
• C10M 125/10 - Oxydes, hydroxydes, carbonates, bicarbonates, métalliques
• C10M 127/02 - Compositions lubrifiantes caractérisées en ce que l'additif est un hydrocarbure non macromoléculaire aliphatique défini
• C10M 129/08 - Composés hydroxylés comportant des groupes hydroxyle liés à des atomes de carbone acycliques ou cycloaliphatiques contenant au moins 2 groupes hydroxyle
• C10M 135/10 - Acides sulfoniques ou leurs dérivés
• C10M 135/36 - Composés hétérocycliques contenant du soufre, du sélénium ou du tellure le cycle contenant du soufre et du carbone ainsi que de l'azote ou de l'oxygène
• C10M 141/08 - Compositions lubrifiantes caractérisées en ce que l'additif est un mélange d'au moins deux composés couverts par plus d'un des groupes principaux , chacun de ces composés étant un composé essentiel l'un d'eux, au moins, étant un composé organique contenant du soufre, du sélénium ou du tellure
• C10M 159/06 - Cires, p. ex. ozocérite, cérésine, gelée de pétrole ou paraffine non deshuilée
• C10M 163/00 - Compositions lubrifiantes caractérisées en ce que l'additif est un mélange d'un composé de constitution indéterminée ou incomplètement déterminée et d'un composé non macromoléculaire, chacun de ces composés étant un composé essentiel
• C10N 40/20 - Travail des métaux
• C10N 30/06 - OnctuositéRésistance du filmAnti-usureRésistance aux pressions extrêmes
• C10N 30/12 - Inhibition de la corrosion, p. ex. agents antirouille, agents anticorrosifs

Abrégé

The present invention relates to oxide nuclear fuel pellets and a preparation method thereof, the oxide nuclear fuel pellets in which, inside the matrix of uranium dioxide pellets used as a nuclear fuel for a nuclear power plant, plate-shaped fine precipitates are uniformly precipitated in the nuclear fuel pellet structures to be dispersed in the form of donut-shaped precipitate clusters. More specifically, by uniformly precipitating plate-shaped fine precipitates in nuclear fuel pellet structures or forming and dispersing donut-shaped two-dimensional precipitate clusters in order to enhance the thermal and physical performance of the uranium dioxide nuclear fuel pellets, the creep strain and thermal conductivity of the uranium dioxide nuclear fuel pellets, which exhibit safety degradation due to a low creep strain and thermal conductivity, are enhanced, thereby reducing pellet-clad interaction damage and nuclear fuel core temperature in an accident, and thus radically enhancing the safety of a nuclear reactor.

Classes IPC  ?

• G21C 3/62 - Combustible céramique

Abrégé

Provided is a nuclear-fuel sintered pellet based on oxide in which a plate-type fine precipitate material in a base of a sintered pellet of uranium dioxide, used as nuclear fuel in nuclear power plants, is uniformly dispersed in a matrix of uranium dioxide fuel thereof so as to form a donut-shaped precipitate cluster, and to a method of manufacturing the same. The plate-type fine precipitate material is uniformly precipitated in a tissue thereof or forms a donut-shaped precipitate cluster having a two-dimensional structure through dispersion to improve thermal and physical performance of the nuclear-fuel sintered pellet of uranium dioxide, whereby the creep deformation rate and thermal conductivity of the sintered pellet are improved. The nuclear-fuel sintered pellet based on oxide can reduce the Pellet-Clad Interaction (PCI) failure and the core temperature of nuclear fuel when an accident occurs, thereby significantly improving the safety of a nuclear reactor.

Classes IPC  ?

• G21C 3/04 - Détails de structure
• G21C 3/60 - Combustible métalliqueDispersions intermétalliques
• G21C 3/62 - Combustible céramique

Abrégé

The present invention relates to a ferritic alloy exhibiting excellent tolerance to a nuclear power plant accident, and a method for manufacturing nuclear fuel cladding using same. Specifically, the present invention relates to providing a ferritic alloy exhibiting excellent accident tolerance, and a method for manufacturing nuclear fuel cladding using same. The alloy comprises iron (Fe), aluminum (Al), chromium (Cr) and nickel (Ni).

Classes IPC  ?

• C22C 38/40 - Alliages ferreux, p. ex. aciers alliés contenant du chrome et du nickel
• C22C 38/60 - Alliages ferreux, p. ex. aciers alliés contenant du plomb, du sélénium, du tellure, de l'antimoine, ou plus de 0,04% en poids de soufre
• C21D 8/06 - Modification des propriétés physiques par déformation en combinaison avec, ou suivie par, un traitement thermique pendant la fabrication de barres ou de fils
• C21D 8/02 - Modification des propriétés physiques par déformation en combinaison avec, ou suivie par, un traitement thermique pendant la fabrication de produits plats ou de bandes
• C21D 1/773 - Procédés de traitement en gaz neutre, en atmosphère contrôlée, sous vide ou dans des matières pulvérulentes sous pression réduite ou sous vide

Abrégé

Embodiments of the disclosure relate to a ferritic alloy having excellent ability to withstand nuclear power plant accidents and a method of manufacturing a nuclear fuel cladding tube using the same. The alloy includes iron (Fe), aluminum (Al), chromium (Cr), and nickel (Ni). The nickel (Ni) may be included 0.5 to 10 wt % based on a total amount of the alloy. The chromium may be included 13 to 18 wt % based on the total amount of the alloy. The aluminum may be included 5 to 7 wt % based on the total amount of the alloy.

Classes IPC  ?

• C22C 38/40 - Alliages ferreux, p. ex. aciers alliés contenant du chrome et du nickel
• C22C 38/00 - Alliages ferreux, p. ex. aciers alliés
• C22C 38/04 - Alliages ferreux, p. ex. aciers alliés contenant du manganèse
• C22C 38/06 - Alliages ferreux, p. ex. aciers alliés contenant de l'aluminium
• C21D 8/10 - Modification des propriétés physiques par déformation en combinaison avec, ou suivie par, un traitement thermique pendant la fabrication de corps tubulaires

Abrégé

The present invention relates to an ISOL system target material, and more specifically relates to a method in which a large-area MWCNT/uranium oxide disc is produced, and the disc is heat treated, thereby producing a uranium carbide/MWCNT disc, and also to a disc produced via the method.

Classes IPC  ?

• B82Y 40/00 - Fabrication ou traitement des nanostructures
• G21G 1/10 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs à l'extérieur des réacteurs nucléaires ou des accélérateurs de particules par bombardement avec des particules électriquement chargées
• H05H 6/00 - Cibles pour la production de réactions nucléaires

Abrégé

The present invention relates to a transfer device which can safely transfer a uranium target, which is to be transferred, by solving a problem caused by physical or chemical properties of the uranium target. The transfer device comprises: an external case, at least one surface of which is open; a cover part which can open or close the open surface of the external case; a fastening part for fastening and fixing the external case and the cover part; a fixing part which is formed inside the external case and fixes an object to be transferred; and a pressure management part formed outside the external case and including a port communicating with a space inside the external case.

Classes IPC  ?

• G21F 5/015 - Récipients blindés portatifs ou transportables pour le stockage de sources radioactives, p. ex. supports de sources pour unités d'irradiationRécipients pour radio-isotopes

Abrégé

The present invention relates to a transfer device which can safely transfer a uranium target, which is to be transferred, by solving a problem caused by physical or chemical properties of the uranium target. The transfer device comprises: an external case, at least one surface of which is open; a cover part which can open or close the open surface of the external case; a fastening part for fastening and fixing the external case and the cover part; a fixing part which is formed inside the external case and fixes an object to be transferred; and a pressure management part formed outside the external case and including a port communicating with a space inside the external case.

Classes IPC  ?

• G21F 5/015 - Récipients blindés portatifs ou transportables pour le stockage de sources radioactives, p. ex. supports de sources pour unités d'irradiationRécipients pour radio-isotopes

Abrégé

The present invention relates to an ISOL system target material, and more specifically relates to a method in which a large-area MWCNT/uranium oxide disc is produced, and the disc is heat treated, thereby producing a uranium carbide/MWCNT disc, and also to a disc produced via the method.

Classes IPC  ?

• G21G 1/04 - Dispositions pour la conversion des éléments chimiques par rayonnement électromagnétique, radiations corpusculaires ou bombardement par des particules, p. ex. production d'isotopes radioactifs à l'extérieur des réacteurs nucléaires ou des accélérateurs de particules
• 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

Abrégé

Provided is a statistical overpower penalty calculation system for a generic thermal margin analysis model, the system including: a random number generating unit generating a plurality of random numbers; an power distribution generating unit generating power information of an axial direction and a radial direction for a core burnup; an operating condition generating unit extracting an arbitrary value for a plurality of operating conditions from the random number generated above; a POL calculating unit calculating a POL of a reload core thermal margin analysis model and a POL of a generic thermal margin analysis model and calculating a plurality of the overpower penalties through the POLs; and a statistics processing unit calculating tolerance limit values according to the core burnup by statistically analyzing a distribution formed of the plurality of the overpower penalties and selecting a smallest tolerance limit value as a representative value of the overpower penalties.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• G05B 19/042 - Commande à programme autre que la commande numérique, c.-à-d. dans des automatismes à séquence ou dans des automates à logique utilisant des processeurs numériques
• G06F 7/58 - Générateurs de nombres aléatoires ou pseudo-aléatoires
• G21D 3/00 - Commande des installations à énergie nucléaire
• G21D 3/04 - Dispositions de sécurité

Abrégé

The present invention relates to a light-water reactor nuclear fuel rod loading force measuring apparatus, and more specifically, to a light-water reactor nuclear fuel rod loading force measuring apparatus which provides the same environment of loading nuclear fuel rods in a spacer grid so that, by conducting a nuclear fuel rod loading force test for each cell of the spacer grid, a data foundation enabling the optimization of a nuclear fuel assembly process may be provided. Provided is a light-water reactor nuclear fuel rod loading force measuring apparatus which is provided with a nuclear fuel rod loading apparatus comprising: a spacer grid holder; and a loading power apparatus provided with a traction module reciprocally moving toward the spacer grid holder. The light-water reactor nuclear fuel rod loading force measuring apparatus comprises: a hollow cladding tube sample which is positioned on one side of a spacer grid and has the same diameter as that of a nuclear fuel rod cladding tube; a pulling bar which has one end part thereof pass through a cell of the spacer grid and coupled to the nuclear fuel rod cladding tube sample, and the other end part thereof coupled to the traction module; and a measuring means which is installed on the pulling bar and measures the force of the traction module pulling the pulling bar.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination

Abrégé

232322 sintering additive is added to uranium dioxide so that a liquid phase generated when sintering the uranium dioxide pellets accelerates mass transfer, thereby promoting the growth of the crystal grains, and also, the low vapor pressure of the liquid phase results in less volatilization during sintering, and thus the additive can exert efficient performance, and as a result, the liquid phase enclosing crystal grain boundaries can effectively adsorb the fission gas cesium.

Classes IPC  ?

• G21C 3/62 - Combustible céramique

Abrégé

223222322. According to the present invention, a liquid, which comprises chromium and manganese oxides in a uranium oxide powder and is to be generated during sintering for preparing nuclear fuel pellets, accelerates the growth of grains and forms a film on a grain boundary so as to inhibit the reaction with stream, thereby inhibiting oxidation, and thus improves high-temperature steam oxidation resistance at around 1204°C (≒ 2200°F), which is the peak cladding temperature (PCT) in a loss-of-coolant accident condition, so that leakage of a fissile material, which is caused by fuel rod damage, can be reduced.

Classes IPC  ?

• G21C 3/62 - Combustible céramique

Abrégé

Provided is an apparatus for fatigue testing a bulge tool having a WH-type skeleton, the apparatus including: a fixing bracket having tool holes penetrated through opposite sides thereof; a tool housing coupled to the tool hole of the fixing bracket and having the bulge tool inserted and installed therein; a moving rail installed at one side of the fixing bracket in a lengthwise direction of the tool housing and providing a reciprocating movement path facing the tool housing; a moving bracket reciprocating along the moving rail; a pusher protrudingly installed from the moving bracket toward the tool housing and moving in and out of the bulge tool; a measurement means installed between the pusher and the moving bracket, measuring a load applied to the bulge tool; and a drive means for generating power reciprocating the moving bracket on the moving rail.

Classes IPC  ?

• G01N 3/08 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique par application d'efforts permanents de traction ou de compression
• G01M 99/00 - Matière non prévue dans les autres groupes de la présente sous-classe
• G01N 3/32 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique en appliquant des efforts répétés ou pulsatoires
• G01B 11/00 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques
• G01N 3/06 - Adaptations particulières des moyens d'indication ou d'enregistrement
• G21C 3/334 - Assemblage des faisceaux

Abrégé

A nuclear fuel rod end distance adjusting device includes an insertion rod, a housing having a hollow space, insertion power means installed inside the housing, a connector connected between the insertion power means and the insertion rod, and an anti-rotation tool installed between the insertion power means and the connector. The insertion rod includes nuclear fuel rod tongs and configured to linearly move forward and backward. The insertion power means is configured to move in a longitudinal direction of the housing by converting a rotational motion into a linear motion. The anti-rotation tool is configured to move in the longitudinal direction of the housing by being interlocked with the linear motion of the insertion power means, but preventing rotational force of the insertion power means from being transmitted to the connector. Thereby, movement and end distance of the fuel rods can be more minutely and stably adjusted.

Classes IPC  ?

• G21C 19/10 - Dispositifs de relèvement ou d'enlèvement adaptés pour coopérer avec les éléments combustibles ou avec l'élément de commande
• G21C 3/334 - Assemblage des faisceaux
• G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
• G21C 7/30 - Commande de la réaction nucléaire par déplacement du combustible du réacteur ou des éléments combustibles

Abrégé

The present invention relates to a support lattice of a nuclear fuel assembly, which can be manufactured by using 3D printing with high design freedom without sheet metal processing or welding processing. The support lattice of a nuclear fuel assembly of the present invention has hollow lattice cells (110) with an inner wall (111), arranged in a square lattice structure and connected by touching each other externally, each lattice cell (110) comprising: a plurality of elastic support parts (112) which are formed to protrude and curve inwardly from the inner wall (111) and which elastically support a fuel rod (10) as at least three elastic support parts are arranged equiangularly; and a plurality of inner mixing vanes (113) the upper end of which is formed to protrude and spiral along the inner wall above the elastic support parts (112).

Classes IPC  ?

• G21C 3/356 - Grilles d'espacement munies d'organes de support des éléments combustibles

Abrégé

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

Classes IPC  ?

• G21C 3/334 - Assemblage des faisceaux
• 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

Abrégé

System for separating and coupling a nuclear fuel assembly from/to a top nozzle which has a flow channel plate with guide holes. The system includes a lock insert and a separation member. The lock insert includes an insertion part provided on a top portion of a hollow body. The separation member is configured to separate the insertion part from a guide hole. The insertion part is variable in size. The insertion part comprises a first latching member and a second latching member, each having a step which contacts the flow channel plate. The first latching member includes a latching groove which is inserted into a member protruding from the top surface of the flow channel plate. The second latching member contacts a bottom surface of the flow channel plate. The separation member provides a space accommodating an outer circumferential surface of the first latching member.

Classes IPC  ?

• 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

Abrégé

Provided is a standard for mobile equipment for measuring structural deformation of a nuclear fuel assembly, the standard including: a fixed frame fixed to one side of measuring equipment accommodated in a container; a standard member configured to be attached to and detached from the fixed frame, to rotate with one end portion of the fixed frame as a center, and to correspond to a nuclear fuel assembly standard specification, wherein an upper plate provided with a coupling means configured to be coupled with a transport device is coupled on one end portion of the standard member, a lower plate configured to be erected upright on and fixed to one side of the measuring equipment is coupled on an opposite end portion of the standard member.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• G01B 11/16 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la déformation dans un solide, p. ex. indicateur optique de déformation

Abrégé

The present invention relates to a fixing device for handling a spent nuclear fuel assembly and a method for installing same, wherein a guide tube and an upper-end fixing body of the spent nuclear fuel assembly can be fixed so as to improve structural reliability. The fixing device according to the present invention comprises: a housing (100) comprising multiple free end portions (110) divided by slots (111) to be able to elastically deform in the radial direction, the slots (111) being formed by incising a hollow cylindrical body (101) from the front end of one side thereof in the longitudinal direction over a predetermined range (L), the housing (100) comprising stopper protrusions (120) formed to protrude from respective front ends of the free end portions (110) in the radial direction, the housing (100) comprising a first male thread (131) formed on the outer peripheral surface of the rear end of the cylindrical body (101), the housing (100) comprising a female thread (132) formed on the inner peripheral surface of the rear end of the cylindrical body (101); a rod portion (200) comprising a pressurization protrusion (210) having a length larger than that of the housing (100) and having an outer diameter (D6) larger than the inner diameter (D5) of the free end portions (110), the rod portion (200) having a second male thread (220) formed on the rear end thereof and screw-assembled with the female thread (132) such that the rod portion (200) is screw-assembled with the housing (100); and fixing members (310) (320) screw-assembled with the first male thread (131) of the housing (100) so as to fix the housing (100) to the nuclear fuel assembly.

Classes IPC  ?

• 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

Abrégé

Embodiments of a bottom nozzle of a nuclear fuel assembly provided with flow holes by utilizing a layered aircraft airfoil structure are provided. The bottom nozzle not only increases efficiency of filtering foreign substances by minimizing a size of the flow holes by constituting a shape of flow holes into cross stripes but also prevents coolant water flow velocity drop through prevention of coolant water pressure drop by constituting a lateral sectional shape of the grid frames constituting the cross stripes into an aircraft airfoil type.

Classes IPC  ?

• G21C 3/32 - Faisceaux d'éléments combustibles en forme d'aiguilles, de barres ou de tubes parallèles
• 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

Abrégé

Provided is mobile equipment for measuring structural deformation of a nuclear fuel assembly, the mobile equipment including: a container; a power means and a loading table disposed inside the container; a pedestal disposed on one side of the loading table of the container, the pedestal being provided with a hinge means and a fixing means configured to fix the nuclear fuel assembly upright; a column seated on the loading table and provided at one end part thereof with a rotating shaft detachably installed to the hinge means, and configured to be erected upright on the fixing means of the pedestal by power of the power means; and a scanner configured to move upward and downward in a longitudinal direction of the column and to measure the structural deformation of the nuclear fuel assembly.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• G01B 11/16 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la déformation dans un solide, p. ex. indicateur optique de déformation

Abrégé

A method of manufacturing a zirconium alloy for a nuclear fuel cladding tube includes melting a mixture of 0.5 wt % of Nb, 0.4 wt % of Mo, 0.1 to 0.15 wt % of Cu, 0.15 to 0.2 wt % of Fe, and a balance of zirconium to prepare a melted ingot; heat treating the melted ingot at 1,000 to 1,050° C. for 30 to 40 min. followed by quenching in water to prepare a heat-treated ingot; preheating the heat-treated ingot at 630 to 650° C. for 20 to 30 min. to prepare a preheated ingot followed by hot rolling the preheated ingot at a reduction ratio of 60 to 65% to provide a hot-rolled material; thrice performing vacuum annealing followed by cold-rolling; and vacuum annealing a third cold-rolled material in a final vacuum annealing at 510 to 520° C. for 7 to 9 hrs. to provide the zirconium alloy as a cold-rolled material.

Classes IPC  ?

• G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
• C22C 16/00 - Alliages à base de zirconium
• C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
• G21C 21/10 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par extrusion, filage, étirage
• B22D 7/00 - Coulée de lingots
• B22D 21/00 - Coulée de métaux non ferreux ou de composés métalliques, dans la mesure où leurs propriétés métallurgiques affectent le procédé de couléeUtilisation de compositions appropriées

Abrégé

The present invention relates to a system for sensing a UF6 leak in a nuclear fuel manufacturing process and, more specifically, to a system, for sensing a UF6 leak in a nuclear fuel manufacturing process, which senses whether or not there is a UF6 leak by optically detecting UO2F2 in a solid state generated due to a reaction with the outside air, and thus allows prevention of damage to a detection apparatus by means of sensing in a non-contact manner whether or not there is a UF6 leak, and allows extension of mechanical life and reduction of the maintenance and repair cost for the detection apparatus.

Classes IPC  ?

• G01M 3/38 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation de la lumière
• G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci
• G01M 3/20 - Examen de l'étanchéité des structures ou ouvrages vis-à-vis d'un fluide par utilisation d'un fluide ou en faisant le vide par détection de la présence du fluide à l'emplacement de la fuite en utilisant des révélateurs particuliers, p. ex. teinture, produits fluorescents, produits radioactifs

Abrégé

The present invention provides a silicon carbide sintered body formed with a plurality of grains made of silicon carbide concentrated close to each other, the silicon carbide sintered body having, on boundary surfaces of the grains forming the sintered body and at a junction at which the boundary surfaces of the grains meet, elements Sc and Y in a rich phase without melting into the grains, thereby allowing sintering at a temperature equal to or less than 1950 ℃, while forming, without EB coating processing, an EB layer comprising on the surface thereon a rare earth-Si oxide comprising elements Sc and Y. In addition, the silicon carbide sintered body reduces the possibility of separation of the EB layer as the EB layer extends into the inner regions of the silicon carbide matrix and forms a strong three-dimensional bond, and, when separation does occur, a new EB layer is formed, thereby greatly increasing the resistance of a silicon carbide material against corrosion due to oxidation, and the use temperature of the silicon carbide material can be increased by preventing oxidation of the silicon carbide material.

Classes IPC  ?

• C04B 35/575 - Céramiques fines obtenues par frittage sous pression
• C04B 35/63 - Préparation ou traitement des poudres individuellement ou par fournées utilisant des additifs spécialement adaptés à la formation des produits
• C04B 35/626 - Préparation ou traitement des poudres individuellement ou par fournées

Abrégé

23232 2 sintering additive is added to uranium dioxide, so that a liquid generated upon sintering of the uranium dioxide pellets accelerates mass transfer to promote the growth of crystal grains and a low vapor pressure of the liquid results in less volatilization during sintering, and thus the additive can exert efficient performance, and as a result, the liquid enclosing crystal grain boundaries can effectively adsorb the fission gas cesium.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
• C01G 43/025 - Dioxyde d'uranium

Abrégé

The present invention relates to an apparatus for fatigue testing a bulge tool having a WH-type skeleton and, more particularly, to an apparatus for fatigue testing a bulge tool having a WH-type skeleton and which is capable of: repeatedly applying a load to a boundary between a bulge and a slot of the bulge tool to measure a fatigue degree of the bulge tool, thereby both promoting the development of technology for improving the quality of bulge tool production and testing the quality of a bulge tool prototype. To this end, provided is an apparatus for fatigue testing a bulge tool having a WH-type skeleton, comprising: a fixing bracket having a tool hole penetrated through both sides thereof; a tool housing coupled to the tool hole of the fixing bracket and having a bulge tool inserted and installed so as to expose the bulge of the bulge tool through one side thereof; a moving rail installed at one side of the fixing bracket in the lengthwise direction of the tool housing and providing a reciprocating movement path toward the tool housing; a moving bracket reciprocating along the moving rail; a pusher protruding from the moving bracket toward the tool housing and moving in and out of the bulge tool by the reciprocating movement of the moving bracket; a measurement means installed between the pusher and the moving bracket, for measuring a load applied to the bulge tool while the pusher moves in and out of the bulge tool; and a drive means for generating power for reciprocating the moving bracket on the moving rail.

Classes IPC  ?

• G01N 3/32 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique en appliquant des efforts répétés ou pulsatoires
• G01N 3/08 - Recherche des propriétés mécaniques des matériaux solides par application d'une contrainte mécanique par application d'efforts permanents de traction ou de compression
• G21C 3/334 - Assemblage des faisceaux

Abrégé

A device for maintaining the internal temperature of a pressure vessel. The device includes a pressure vessel equipped with a main heater for heating test water to a predetermined test temperature and for maintaining the predetermined test temperature, a preheater for primarily heating the test water to the predetermined test temperature before the main heater heats the test water, and a heat exchanger including an feed pipe for feeding the test water heated by the preheater to the pressure vessel and a discharge pipe for transporting the test water discharged from the pressure vessel, in which the feed pipe is disposed inside the discharge pipe.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• F17C 1/12 - Récipients sous pression, p. ex. bouteilles de gaz, réservoirs de gaz, cartouches échangeables avec des moyens pour assurer une isolation thermique
• G01N 17/02 - Systèmes de mesure électro-chimique de l'action due aux intempéries, de la corrosion ou de la protection contre la corrosion

Abrégé

22 powder, the sintered body consisting of a dish (10) having both ends of a cylindrical shape formed by spherical grooves, wherein the centers of the both end surfaces have a constant curved surface; a shoulder (20) circularly formed along the rim of the dish (10) having a constant width, which is perpendicular to the cylindrical shape; and a chamfer (30) formed as a chamfered edge along the rim of the shoulder (20). Provided is a nuclear fuel sintered body having excellent impact resistance, wherein the width (SW) of the shoulder (20) is 0.20 mm to 0.80 mm and the angle between the chamfer (30) and the horizontal plane is 14° to 18°, thereby enhancing the impact strength of the sintered body as the shape of the sintered body is improved, so as to minimize the Pellet-Clad Mechanical Interaction (PCMI) damage by means of a missing pellet surface (MPS).

Classes IPC  ?

• G21C 3/04 - Détails de structure
• C04B 35/10 - Produits céramiques mis en forme, caractérisés par leur compositionCompositions céramiquesTraitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base d'oxydes à base d'oxyde d'aluminium
• C04B 38/06 - Mortiers, béton, pierre artificielle ou articles de céramiques poreuxLeur préparation en éliminant par brûlage des substances ajoutées

Abrégé

The present invention provides a nuclear fuel pellet having excellent compression resistance and a reduced surface defect. The upper surface and the bottom surface of the nuclear fuel pellet, which is in a cylindrical shape, comprises: a dish in a spherical groove shape having a fixed curved surface on the center; a land in a horizontal ring shape along the rim of the dish; and a chamfer of which the edge is chamfered at a fixed angle along the land rim. The chamfer comprises: a primary chamfer adjacent to the land rim; and a secondary chamfer additionally chamfered along the edge of the primary chamfer.

Classes IPC  ?

• G21C 3/04 - Détails de structure
• G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives

Abrégé

The present invention relates to a nuclear fuel rod end distance adjusting device and, more specifically, to a nuclear fuel rod end distance adjusting device capable of more minutely adjusting a movement length of a loading bar by means of the configuration of a loading power means depending on a change of a rotational motion to a linear motion and preventing the rotational motion of the loading power means from being transmitted to the loading bar such that the end distance of a nuclear fuel rod can be stably adjusted. To this end, the nuclear fuel rod end distance adjusting device comprises: a loading bar which includes nuclear fuel rod tongs and is linearly movable in the forward and backward directions; a hollow housing; a loading power means which is installed inside the housing and converts a rotational motion to a linear motion so as to move in the longitudinal direction of the housing; a connector connected between the loading power means and the loading bar; and a rotation prevention device which is installed between the loading power means and the connector and moves in the longitudinal direction of the housing in conjunction with the linear motion of the loading power means, wherein the rotation prevention device prevents the rotational force of the loading power means from being transmitted to the connector..

Classes IPC  ?

• 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

Abrégé

2232222322 of 10-10to 10-7. According to the present invention, silicon, manganese and chromium oxides are contained in a uranium oxide powder, and a liquid to be generated during sintering for manufacturing sintered nuclear fuel pellets accelerates the growth of grains and also forms a film on the interface of the grains, thereby limiting an oxidation reaction by inhibiting a reaction with steam, and thus high-temperature steam oxidation resistance is improved near 1,204°C (≒ 2,200°F), which is the peak cladding temperature (PCT) under a coolant-loss accident condition, such that the leakage of fissile material caused by fuel rod damage can be reduced.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• C04B 35/01 - Produits céramiques mis en forme, caractérisés par leur compositionCompositions céramiquesTraitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base d'oxydes
• C04B 35/64 - Procédés de cuisson ou de frittage

Abrégé

Disclosed is a device for controlling an interface of a liquid-liquid extraction column using pressure equilibrium. The device includes a vertical pipe provided beside an extraction column parallel thereto. The device enables internal pressures of the extraction column and the vertical pipe to be balanced with each other by moving fluid from the extraction column into the vertical pipe. Therefore, the device can maintain the level of an interface between fluids having different specific gravities with a simple control system. The device includes the liquid-liquid extraction column having a column body; and upper and lower tanks having respective inlet pipes and respective outlet pipes, wherein a pipeline is connected to the outlet pipe of the lower tank, and the internal pressures are balanced by controlling a level of the fluid in the pipeline, thereby maintaining the level of the interface.

Classes IPC  ?

• B01D 11/04 - Extraction par solvants de solutions
• G05D 16/00 - Commande de la pression d'un fluide

Abrégé

The present invention particularly relates to a method for measuring the degree of recrystallization of a zirconium alloy cladding tube for a nuclear fuel by using EBSD pattern quality, and the objective of the present invention is to provide a method for measuring the degree of recrystallization of a zirconium alloy cladding tube for a nuclear fuel, the method being capable of more accurately obtaining a degree of recrystallization than a conventional method for calculating a degree of recrystallization by using pattern quality, by comprising: a first step of electrolytic polishing a fully recrystallized sample 1, a partially recrystallized sample 2 of which a recrystallization measurement is needed, and an As-deformed sample 3, then making an SEM electron beam incident to each of sample 1 to sample 3 at a predetermined scan interval, and then acquiring a backscattered electron signal through an EBSD camera; a second step of using EBSD software so as to convert the backscattered electron signals acquired from sample 1 to sample 3 into pattern quality values, and calculating the pattern quality values as frequencies within a specific range; a third step of obtaining a pattern quality frequency (B+D) deviated from a frequency of sample 3 among a total frequency distribution of sample 2 and obtaining a pattern quality frequency (D+E) deviated from the frequency of sample 3 among a total frequency distribution of sample 1; and a fourth step of obtaining a degree of recrystallization of sample 2 from equation X'=(B+D)/(D+E)×100,%.

Classes IPC  ?

• G01N 23/203 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffraction de la radiation par les matériaux, p. ex. pour rechercher la structure cristallineRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffusion de la radiation par les matériaux, p. ex. pour rechercher les matériaux non cristallinsRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la réflexion de la radiation par les matériaux en mesurant la rétrodiffusion
• G01N 23/20 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffraction de la radiation par les matériaux, p. ex. pour rechercher la structure cristallineRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffusion de la radiation par les matériaux, p. ex. pour rechercher les matériaux non cristallinsRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la réflexion de la radiation par les matériaux
• G01N 23/205 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffraction de la radiation par les matériaux, p. ex. pour rechercher la structure cristallineRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffusion de la radiation par les matériaux, p. ex. pour rechercher les matériaux non cristallinsRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la réflexion de la radiation par les matériaux en utilisant des caméras de diffraction

Abrégé

The present invention relates to a recrystallization rate measurement method of zirconium alloy cladding of a nuclear fuel rod, the method including: step 1 of irradiating SEM electron beams at a given scanning interval onto a first specimen to a third specimen which were electrolytically polished and obtaining electron backscattered signals therefrom by an EBSD camera; step 2 of converting electron backscattered signals obtained in step 1 into pattern quality values, respectively, and generating the pattern quality values as frequencies by a specified interval; step 3 of obtaining pattern quality frequencies (B+D) which are a portion of a whole frequency distribution of the second specimen, and pattern quality frequencies (D+E) which are a portion of a whole frequency distribution of the first specimen; and step 4 of obtaining the recrystallization rate of the second specimen with an equation of .

Classes IPC  ?

• G01N 23/2251 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en mesurant l'émission secondaire de matériaux en utilisant des microsondes électroniques ou ioniques en utilisant des faisceaux d’électrons incidents, p. ex. la microscopie électronique à balayage [SEM]
• G01N 23/203 - Recherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffraction de la radiation par les matériaux, p. ex. pour rechercher la structure cristallineRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la diffusion de la radiation par les matériaux, p. ex. pour rechercher les matériaux non cristallinsRecherche ou analyse des matériaux par l'utilisation de rayonnement [ondes ou particules], p. ex. rayons X ou neutrons, non couvertes par les groupes , ou en utilisant la réflexion de la radiation par les matériaux en mesurant la rétrodiffusion
• G01N 33/20 - Métaux

Abrégé

Disclosed is a system for decoupling and coupling an upper end fitting of a nuclear fuel assembly. In the present invention, a lock insert, which is coupled to a guide hole formed on a flow channel plate of an upper end fitting of a nuclear fuel assembly and supports the upper end fitting, is characterized by comprising: a hollow body; and an insertion part provided in an upper portion of the body and inserted into the guide hole, wherein the insertion part is inserted into the guide hole by varying the circumference of the insertion part. According to the present invention, disassembly and reassembly of the upper end fitting of the nuclear fuel assembly and the lock insert are simplified to simplify and reduce the number of processes involved, and thus the system is effective for the maintenance and repair of the nuclear fuel assembly.

Classes IPC  ?

• 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

Abrégé

A lock insert of a nuclear fuel assembly upper fixture is disclosed. The present invention relates to the lock insert, which is coupled to a guide hole formed at a channel plate of the nuclear fuel assembly upper fixture so as to support the upper fixture, and includes a hollow body and an insertion part provided at the upper part of the body and inserted in the guide hole, wherein the insertion part varies in circumference size so as to be inserted into the guide hole. A separating/coupling system of the nuclear fuel assembly upper fixture, including the lock insert of the nuclear fuel assembly upper fixture, is disclosed. The present invention comprises: the upper fixture; the channel plate provided at the lower part of the upper fixture so as to allow cooling water to flow; the guide hole formed at the channel plate; the hollow lock insert including the insertion part to be inserted into the guide hole; and a separating member for separating the lock insert from the guide hole, wherein the insertion part of the lock insert varies in circumference size so as to be inserted in or separated from the guide hole. Additionally, the present invention simplifies an operation for disassembling and re-assembling the nuclear fuel assembly upper fixture and the lock insert so as to make the operation convenient and reduce man-hours, thereby being effective in maintaining and repairing the nuclear fuel assembly.

Classes IPC  ?

• 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

Abrégé

Provided are embodiments of a pressure-compensated load transfer device that includes a plate having a first shaft vertically installed on one side and a second shaft vertically installed on the other side to be coaxial with the first shaft. Also included is a first bellows having an opening in one side to surround the first shaft, with the other side thereof being fixed to the one side of the plate. Further included is a plurality of second bellows each having an opening in one end, with the other end thereof being attached to the other side of the plate. A housing is also included, and the housing includes a high-pressure working hole communicating with the opening of the first bellows and a high-pressure channel coplanar with the high-pressure working hole and communicating with the openings of the second bellows. The plate is back-and-forth movably received in the housing.

Classes IPC  ?

• F04B 45/02 - Pompes ou installations de pompage, ayant des organes de travail flexibles, spécialement adaptées pour fluides compressibles ayant des soufflets
• F15B 15/14 - Dispositifs actionnés par fluides pour déplacer un organe d'une position à une autreTransmission associée à ces dispositifs caractérisés par la structure de l'ensemble moteur le moteur étant du type à cylindre droit
• F16H 35/00 - Transmissions ou mécanismes ayant d'autres caractéristiques de fonctionnement particulières
• F15B 13/02 - Dispositifs de distribution ou d'alimentation du fluide caractérisés par leur adaptation à la commande de servomoteurs
• F15B 15/17 - Dispositifs actionnés par fluides pour déplacer un organe d'une position à une autreTransmission associée à ces dispositifs caractérisés par la structure de l'ensemble moteur le moteur étant du type à cylindre droit du type à piston différentiel

Abrégé

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

Classes IPC  ?

• G21F 9/08 - Traitements par évaporationTraitements par distillation
• B01D 35/02 - Filtres adaptés à des endroits particuliers, p. ex. conduites, pompes, robinets
• G01T 1/167 - Mesure du contenu radioactif des objets, p. ex. contamination
• G21F 9/10 - Traitements par floculation
• C02F 1/58 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par élimination de composés spécifiés dissous
• C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
• C02F 9/00 - Traitement en plusieurs étapes de l'eau, des eaux résiduaires ou des eaux d'égout
• C02F 1/04 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par chauffage par distillation ou évaporation
• C02F 1/52 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par floculation ou précipitation d'impuretés en suspension
• G21F 9/12 - Traitements par absorptionTraitements par adsorptionTraitements par échange d'ions

Abrégé

A correlation tolerance limit setting system using repetitive cross-validation includes: a variable extraction unit randomly classifying data of an initial DB set into training set data and validation set data at a specific rate and then extracting variables for determining a DNBR limit by optimizing coefficients of a selected correlation; a normality test unit testing normality for a variable extraction result; a DNBR limit unit determining whether data sets have a same population or not depending on normality result and determining DNBR limit from a distribution of 95/95 DNBR; and a controller.

Classes IPC  ?

• G21D 3/00 - Commande des installations à énergie nucléaire
• G06K 9/62 - Méthodes ou dispositions pour la reconnaissance utilisant des moyens électroniques
• G06F 17/15 - Calcul de fonction de corrélation
• G06F 17/18 - Opérations mathématiques complexes pour l'évaluation de données statistiques
• G21D 3/06 - Dispositions de sécurité réagissant à des défaillances à l'intérieur de l'installation
• G21D 3/04 - Dispositions de sécurité
• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes

Abrégé

The present invention relates to mobile equipment for measuring structural deformation of a nuclear fuel assembly and, more particularly, to mobile equipment for measuring structural deformation of a nuclear fuel assembly, which measures the length, an envelope and a maximum slope of the nuclear fuel assembly, thereby enhancing the accuracy of measuring the structural deformation of the nuclear fuel assembly, and is configured in a container type so as to be moveable, thereby enhancing an operation efficiency for measurement locations. To this end, provided is mobile equipment for measuring structural deformation of a nuclear fuel assembly, comprising: a container; a power means and a loading stand which are disposed inside the container; a seat disposed at one side of the loading stand in the container and having a hinge means and a fixing means for fixing the nuclear fuel assembly upright; a column which is mounted on the loading stand and has a pivot shaft detachably coupled to the hinge means at one end thereof, wherein the column is erected upright on one side of the fixing means of the seat about the pivot shaft coupled to the hinge means by the power of the power means; and a scanner which is raised or lowered in the longitudinal direction of the column standing upright on the seat and which is for measuring structural deformation of the nuclear fuel assembly standing upright on the fixing means.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• G01B 11/16 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la déformation dans un solide, p. ex. indicateur optique de déformation

Abrégé

The present invention relates to a standard for mobile equipment for measuring structural deformation of a nuclear fuel assembly and, more particularly, to a standard for mobile equipment for measuring structural deformation of a nuclear fuel assembly, which, in order to increase the measurement accuracy of a scanner for measuring the nuclear fuel assembly, has a standard member corresponding to standard specifications of a nuclear fuel assembly so that a scanner correcting operation can be performed. To this end, provided is a standard for equipment for measuring structural deformation of a mobile nuclear fuel assembly, comprising: a fixed frame fixed to one side of equipment for measuring structural deformation of a mobile nuclear fuel assembly which is accommodated inside a container; and a standard member which is attached/detached to/from the fixed frame, is rotated around one end of the fixed frame, and corresponds to standard specifications of the nuclear fuel assembly, wherein the standard member has one end coupled to an upper plate having a coupling means coupled to a conveying device, and the other end coupled to a lower plate for being fixed upright on one side of the equipment.

Classes IPC  ?

• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• G01B 11/16 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la déformation dans un solide, p. ex. indicateur optique de déformation

Abrégé

The present invention relates to a treatment method and a treatment apparatus for UF6 heel, using a gas phase reaction. A specific treatment method comprises the steps of: (1) vaporizing UF6 heel; (2) generating solid UO2F2 by using the vaporized UF6 gas; (3) separating the solid UO2F2 from a by-product gas; and (4) separating hydrogen fluoride from the by-product gas. The treatment apparatus can comprise: (1) a vaporizer used only for vaporizing UF6 heel; (2) a reactor connected to the vaporizer so as to generate UO2F2 by using the UF6 gas generated at the vaporizer; (3) a solid/gas separator connected to the reactor so as to separate the solid UO2F2, which is generated in the reactor, from the by-product gas; (4) a heat exchanger connected to the solid/gas separator so as to allow the by-product gas, which is supplied from the solid/gas separator, to pass therethrough and be condensed into liquid; and (5) a liquid/gas separator for separating the hydrogen fluoride liquid, which is condensed at the heat exchanger, from the gas. According to the present invention, stabilization of a reconversion process and the quality of a UO2 powder can be improved by preparing solid UO2F2, which is an intermediate of the UO2 powder, through UF6 heel treatment, and the high cost of radioactive waste disposal is reduced by minimizing UF6 heel to be less than 0.5 kg.

Classes IPC  ?

• G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
• C01G 43/06 - Fluorures

Abrégé

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.

Classes IPC  ?

• G21F 9/16 - Traitements par fixation dans un milieu solide stable
• C04B 28/06 - Ciments alumineux
• C04B 14/36 - Matières inorganiques non prévues par les groupes
• G21F 9/34 - Moyens de se débarrasser des résidus solides
• C04B 22/14 - Acides ou leurs sels comportant du soufre dans la partie anionique, p. ex. sulfures

Abrégé

m; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• C04B 35/628 - Revêtement des poudres
• C04B 35/626 - Préparation ou traitement des poudres individuellement ou par fournées
• C04B 35/634 - Polymères
• C04B 35/565 - Produits céramiques mis en forme, caractérisés par leur compositionCompositions céramiquesTraitement de poudres de composés inorganiques préalablement à la fabrication de produits céramiques à base de non oxydes à base de carbures à base de carbure de silicium
• C04B 35/632 - Additifs organiques
• C04B 35/645 - Frittage sous pression
• C04B 38/00 - Mortiers, béton, pierre artificielle ou articles de céramiques poreuxLeur préparation
• 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 21/04 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives par compactage ou pilonnage par vibration

Abrégé

The present invention relates to a device for maintaining the internal temperature of a pressure vessel, the device comprising: the pressure vessel having a main heater for heating testing water up to a test temperature and maintaining the same; a preliminary heater for heating the temperature of the testing water to the test temperature before the main heater performs the same; and a heat exchanger including an injection pipe for injecting the testing water of the preliminary heater to the pressure vessel and a discharge pipe through which the testing water of the pressure vessel is discharged, wherein the injection pipe is inserted into the discharge pipe.

Classes IPC  ?

• G01N 17/02 - Systèmes de mesure électro-chimique de l'action due aux intempéries, de la corrosion ou de la protection contre la corrosion
• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination

Abrégé

The present invention relates to a large-particle-size ammonium uranate hydrate crystal, and a preparation method therefor. The present invention, unlike a conventional ADU process in which a uranyl nitrate aqueous solution and ammonia water are reacted, controls a reaction rate by injecting gaseous ammonia into a uranyl nitrate aqueous solution, such that the particle diameter of ammonium uranate hydrate crystals to be generated can be increased, and in the experimental result, the average particle size of finally prepared ammonium uranate hydrate crystals was 9.32-14.68 μm, which is at least 100 times greater than that of crystals prepared by the conventional ADU process. In addition, in a filtrate analysis result, the uranium content was less than 1 ppm. Since the diameter of the ammonium uranate hydrate crystals prepared according to the present invention is very large compared to those of the conventional crystals, handling in filtration, drying and roasting/reduction processes, which are subsequent processes, is much easier than in the conventional ADU process and designing apparatuses for the subsequent processes is also simpler than that of the conventional process, and since a filtrate generated in a filtration process hardly contains uranium, a separate chemical treatment process for uranium recovery is unnecessary, and thus facility investment costs can be greatly reduced.

Classes IPC  ?

• C01G 43/00 - Composés de l'uranium
• G21C 3/46 - Compositions aqueuses

Abrégé

x) can be analyzed only in a pellet state and a subsequent treatment process needs to be performed according to the analysis result.

Classes IPC  ?

• G01J 3/427 - Spectrométrie à double longueur d'onde
• G01N 33/22 - CombustiblesExplosifs
• G01N 9/24 - Recherche du poids spécifique ou de la densité des matériauxAnalyse des matériaux en déterminant le poids spécifique ou la densité en observant la propagation de l'onde ou de la radiation des particules à travers le matériau
• G01N 21/31 - CouleurPropriétés spectrales, c.-à-d. comparaison de l'effet du matériau sur la lumière pour plusieurs longueurs d'ondes ou plusieurs bandes de longueurs d'ondes différentes en recherchant l'effet relatif du matériau pour les longueurs d'ondes caractéristiques d'éléments ou de molécules spécifiques, p. ex. spectrométrie d'absorption atomique
• G21C 17/06 - Dispositifs ou dispositions pour la surveillance ou le test du combustible ou des éléments combustibles en dehors du cœur du réacteur, p. ex. pour la consommation ou pour la contamination
• G21C 3/26 - Éléments combustibles avec un matériau fissile ou surrégénérateur sous forme de poudre à l'intérieur d'une enveloppe non active
• G01N 33/00 - Recherche ou analyse des matériaux par des méthodes spécifiques non couvertes par les groupes
• G21C 3/04 - Détails de structure

Abrégé

The present invention relates to a modular extraction tower (1), as a modularized extraction tower, which is easily manufactured and provided and enables convenient maintenance and repair work, such as changing of a process or an inner structure of the extraction tower, replacing of a damaged structure, or decontaminating even after installation, and comprises: a head block (10) having a flange (110) provided on one surface thereof; a body block (20) having mounting modules (210), which are stacked on and assembled with the flange (110), have a first module flange (212) and a second module flange (213) at both sides thereof in different directions along the same axis, have an accommodation part (211) having a predetermined area and formed therein, and are coupled to each other, such that the first module flange (212) and the second module flange (213) face each other; and an inner structure provided in the accommodation part (211) and dispersing fluid, wherein the head block (10) and the body block (20) communicate with each other, and the accommodation part (211) has a square cross section, which is vertical with respect to the longitudinal direction.

Classes IPC  ?

• B01D 11/04 - Extraction par solvants de solutions

Abrégé

The present invention relates to a device for controlling the interface of a liquid-liquid extraction column using a pressure equilibrium and, more particularly, to a device for controlling the interface of a liquid-liquid extraction column wherein a vertical pipe is installed on one side of the extraction column in parallel with the extraction column, and an equilibrium is artificially reached between the pressure acting in the extraction column and the pressure acting in the vertical pipe through a fluid movement from the extraction column to the vertical pipe such that, through a simple control system configuration, a constant interface is maintained between two fluids having different specific gravities introduced into the column top of the extraction column. To this end, there is provided a device for controlling the interface of a liquid-liquid extraction column characterized in that a liquid-liquid extraction column is provided, the liquid-liquid extraction column comprising a column body and a column top and a column bottom that are installed on the upper and lower portions of the top body, respectively, and have an introduction tube and a discharge tube installed therein such that fluids having different specific gravities are introduced and discharged, respectively; a pipeline is connected to the discharge tube of the column bottom such that a fluid discharged through the column bottom ascends through the same; the fluid level is adjusted in response to the rise of the fluid through the pipeline such that an equilibrium is maintained between the pressure inside the extraction column and the pressure inside the pipeline; and, accordingly, a constant interface is maintained between the two fluids having different specific gravities introduced into the column top.

Classes IPC  ?

• B01D 11/04 - Extraction par solvants de solutions

Abrégé

A pressure-compensated load transfer device (1) according to the present invention comprises: a plate (24) having a first shaft (10) vertically installed on one side thereof and a second shaft (14) vertically installed on the other side thereof while being disposed coaxially with the first shaft (10); a first bellows (12) having, on one side thereof, an opening by which the first shaft (10) is surrounded, and fixed on the other side thereof to the side of the plate (24) where the first shaft (10) is installed; a plurality of second bellows (16) each having an opening formed at one end thereof, and attached at the other end thereof to the side of the plate (24) where the second shaft (14) is installed; and a housing which includes a high-pressure working hole (32) communicating with the opening on one side of the first bellows (12) and a high-pressure channel (38) being coplanar with the high-pressure working hole (32) and communicating with openings of the second bellows (16), and in which the plate (24) is back-and-forth movably received.

Classes IPC  ?

• F15B 15/08 - Dispositifs actionnés par fluides pour déplacer un organe d'une position à une autreTransmission associée à ces dispositifs caractérisés par la structure de l'ensemble moteur
• F15B 15/14 - Dispositifs actionnés par fluides pour déplacer un organe d'une position à une autreTransmission associée à ces dispositifs caractérisés par la structure de l'ensemble moteur le moteur étant du type à cylindre droit
• F15B 13/02 - Dispositifs de distribution ou d'alimentation du fluide caractérisés par leur adaptation à la commande de servomoteurs

Abrégé

Provided are a system and a method for detecting a uranium hexafluoride (UF6) leak. The system for detecting a UF6 leak comprises: a vaporizer (10); a cylinder (11) arranged in the vaporizer (10) and accommodating solid state UF6; a heater (12) provided at the vaporizer (10), and heating the nitrogen gas in the vaporizer (10) so as to heat the cylinder (11); and a detecting sensor (13) arranged on the outside of the vaporizer (10), inducing the nitrogen gas in the vaporizer (10), and having an air supply pump (14), which supplies surrounding air to a special dual nozzle (15) such that the UF6 gas reacts with moisture after the end of the nozzle, thereby sensing the existence of HF gas in real time.

Classes IPC  ?

• G21C 17/00 - SurveillanceTests

Abrégé

The present invention relates to a method for collecting uranium (U) by a chemical treatment process of a uranium hexafluoride (UF6) cylinder washing waste liquid, and to an apparatus therefor. According to the present invention, by providing a method and an apparatus wherein uranium (U) is separated from a waste liquid generated in a uranium hexafluoride (UF6) cylinder washing process and a filtrate can be released while satisfying atomic energy licensing and environmental standards through evaporation and condensation, an independent technology and process for disposal of a waste liquid generated in a uranium hexafluoride (UF6) cylinder washing process can be secured; more convenient maintenance through the securing of independent technical skills can be attained; and significant cost savings compared with when foreign company facilities are brought in and operated can be attained.

Classes IPC  ?

• C22B 60/02 - Obtention du thorium, de l'uranium ou des autres actinides
• G21F 9/08 - Traitements par évaporationTraitements par distillation
• G21F 9/10 - Traitements par floculation
• G21F 9/12 - Traitements par absorptionTraitements par adsorptionTraitements par échange d'ions
• C02F 9/00 - Traitement en plusieurs étapes de l'eau, des eaux résiduaires ou des eaux d'égout
• C02F 1/58 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par élimination de composés spécifiés dissous
• C02F 1/52 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par floculation ou précipitation d'impuretés en suspension
• C02F 1/04 - Traitement de l'eau, des eaux résiduaires ou des eaux d'égout par chauffage par distillation ou évaporation
• B01D 35/02 - Filtres adaptés à des endroits particuliers, p. ex. conduites, pompes, robinets
• G01T 1/167 - Mesure du contenu radioactif des objets, p. ex. contamination

Abrégé

The present invention relates to a correlation tolerance limit setting system using repetitive cross-validation and a method therefor and, to a correlation tolerance limit setting system using repetitive cross-validation and a method therefor, the system and the method being for preventing data characteristic distortion due to accidental or human interference in correlation optimization and tolerance limit setting, and for preventing a risk created thereby, or for quantifying the influence thereof. According to the present invention, the correlation tolerance limit setting system using repetitive cross-validation comprises: a variable extraction unit for classifying training sets and validation sets, and optimizing a correlation coefficient so as to extract variables; a normality verification unit for verifying normality in accordance with the variable extraction result; a DNBR limit unit for verifying whether the same population is present according to the normality, and determining a tolerance limit of a departure from a nucleate boiling ratio by using a tolerance limit distribution for a departure from nucleate boiling; and a control unit.

Classes IPC  ?

• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes

Abrégé

A fuel pellet visual inspection device for manufacturing a nuclear fuel rod improves convenience and workability of visual inspection of a plurality of pellets by simultaneously turning over the pellet. The fuel pellet visual inspection device for manufacturing a nuclear fuel rod includes: a rotary shaft; a pair of seats hinged to the hinge shaft, arranged at both sides from the rotary shaft, and seated with a tray thereon; and a dust-collecting unit disposed under the pair of seats and collecting dust scattered from pellets.

Classes IPC  ?

• G01B 11/02 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la longueur, la largeur ou l'épaisseur
• G01N 21/01 - Dispositions ou appareils pour faciliter la recherche optique
• G01N 21/88 - Recherche de la présence de criques, de défauts ou de souillures
• G01N 21/94 - Recherche de souillures, p. ex. de poussières
• G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
• G01N 21/952 - Inspection de la surface extérieure de corps cylindriques ou de fils

Abrégé

A method of monitoring in real time pressure resistance welding of a cladding tube and an end plug. The method includes: a first step of detecting welding information including voltage, current, and welding force in a process of pressure resistance welding of a cladding tube and an end plug; a second step of comparing static factors obtained by calculating effective values for the welding information with predetermined reference values, respectively; a third step of calculating dynamic factors for the welding information including the gradient of instantaneous welding force, when the reference values are satisfied in the second step; and a fourth step of determining whether there is defect or not in welding quality by comparing the dynamic factors.

Classes IPC  ?

• B23K 11/00 - Soudage par résistanceSectionnement par chauffage par résistance
• B23K 11/25 - Dispositifs de surveillance
• B23K 11/093 - Soudage de joints continus non limité à l'un des sous-groupes précédents pour des joints curvilignes situés dans un plan
• G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
• G21C 3/334 - Assemblage des faisceaux
• G21C 3/10 - Obturateurs d'extrémités

Abrégé

The present invention relates to a correlation tolerance limit setting system using repetitive cross-validation and a method therefor and, to a correlation tolerance limit setting system using repetitive cross-validation and a method therefor, the system and the method being for preventing data characteristic distortion due to accidental or human interference in correlation optimization and tolerance limit setting, and for preventing a risk created thereby, or for quantifying the influence thereof. According to the present invention, the correlation tolerance limit setting system using repetitive cross-validation comprises: a variable extraction unit for classifying training sets and validation sets, and optimizing a correlation coefficient so as to extract variables; a normality verification unit for verifying normality in accordance with the variable extraction result; a DNBR limit unit for verifying whether the same population is present according to the normality, and determining a tolerance limit of a departure from a nucleate boiling ratio by using a tolerance limit distribution for a departure from nucleate boiling; and a control unit.

Classes IPC  ?

• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes

Abrégé

The present invention relates to a lower end fitting for reducing flow resistance due to an in-core instrument in a nuclear fuel assembly, that is, a lower end fitting (100) having a plurality of flow holes for a nuclear fuel assembly, in which the flow holes (121) are formed under an assembly groove in which an instrumentation tube (131) for a nuclear fuel assembly is inserted, and at least two or more flow holes (121) are formed at a predetermined distance from the central axis (C) of the instrumentation tube (131).

Classes IPC  ?

• G21C 3/322 - Moyens pour influencer l'écoulement du réfrigérant à travers ou autour des faisceaux
• G21C 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes
• G21C 17/108 - Mesure du flux
• G21C 3/33 - Moyens pour supporter ou suspendre des éléments dans le faisceauMoyens faisant partie du faisceau pour l'insérer dans le cœur ou l'en extraireMoyens de couplage de faisceaux adjacents
• G21C 15/02 - Aménagement ou disposition de passages dans lesquels la chaleur est transférée au réfrigérant, p. ex. pour la circulation du réfrigérant à travers les supports des éléments combustibles

Abrégé

The present invention relates to a top nozzle and a nuclear reactor in which an in-core instrument, which is supposed to be inserted through a top head of a nuclear reactor, is inserted through a guide pin for an upper core plate. In a nuclear reactor including guide pins for aligning a top nozzle for a nuclear fuel assembly with an upper core plate of a nuclear reactor, a guide hole (210) is axially formed through the guide pins (200) and in-core instruments (10) are inserted through the guide holes (210).

Classes IPC  ?

• G21C 17/108 - Mesure du flux
• 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 17/10 - Combinaison structurelle de l'élément combustible, de la barre de commande, du cœur du réacteur, ou de la structure du modérateur avec des instruments sensibles, p. ex. pour la mesure de la radioactivité, des contraintes
• G21C 13/036 - Raccords entre le tube et la paroi d'une enceinte, p. ex. tenant compte des contraintes thermiques le tube traversant la paroi, c.-à-d. s'étendant de chaque côté

Abrégé

The present invention provides a method for manufacturing a zirconium alloy part, the method allowing precipitates having an average size of 35 nm or less to be equally distributed in a matrix through a multi-stage hot-rolling step. Specifically, provided in the present invention is the method for manufacturing the zirconium alloy part, comprising: (step 1) a step of forming an ingot of niobium-contained zirconium alloys; (step 2) a step of thermally treating the ingot, manufactured in step 1, at a beta phase temperature of zirconium, and then rapidly cooling the same; (step 3) a step of preheating the ingot rapidly cooled in step 2, before hot-rolling; (step 4) a multi-stage hot-rolling step of performing primary hot-rolling right after preheating in step 3 is finished, and then performing secondary hot-rolling during air cooling; (step 5) a step of performing primary intermediate thermal treatment for a rolled material hot-rolled in multiple stages in step 4, and then primarily cold-rolling the same; (step 6) a step of performing secondary intermediate thermal treatment for the rolled material primarily cold-rolled in step 5, and then secondarily cold-rolling the same; (step 7) a step of performing tertiary intermediate thermal treatment for the rolled material secondarily cold-rolled in step 6, and then tertiarily cold-rolling the same; and (step 8) a step of finally thermally treating the rolled material tertiarily cold-rolled in step 7. A nuclear fuel zirconium alloy sheet material is manufactured by using the manufacturing method according to the present invention, such that the fine precipitates are formed in the matrix, thereby improving corrosion-resistance performance under a high-temperature vapor condition and increasing resistance to fatigue fracture.

Classes IPC  ?

• C22C 16/00 - Alliages à base de zirconium
• C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
• B21B 3/00 - Laminage des matériaux faits d'alliages particuliers dans la mesure où la nature de l'alliage exige ou permet l'emploi de méthodes ou de séquences particulières
• B21B 37/16 - Commande de l'épaisseur, de la largeur, du diamètre ou d'autres dimensions transversales
• G21C 21/00 - Appareillage ou procédés spécialement adaptés pour la fabrication des réacteurs ou de pièces de ceux-ci

Abrégé

The present invention relates to a solidifying agent for solidifying radioactive waste, and the solidifying-agent composition for solidifying radioactive waste of the present invention comprises alumina cement and a gypsum powder. According to the present invention, a solidifying-agent composition containing alumina cement and a gypsum powder is provided, leading to an effect of minimizing the volume increase of a radioactive waste solidified body at a level that meets physical and chemical safety regulations in the solidification treatment of radioactive waste.

Classes IPC  ?

• G21F 9/16 - Traitements par fixation dans un milieu solide stable
• C04B 28/06 - Ciments alumineux
• C04B 14/36 - Matières inorganiques non prévues par les groupes

Abrégé

The present invention relates to a method for preparing a fully ceramic capsulated nuclear fuel material containing three-layer-structured isotropic nuclear fuel particles coated with a ceramic having a composition which has a higher shrinkage than a matrix in order to prevent cracking of ceramic nuclear fuel, wherein the three-layer-structured nuclear fuel particles before coating is included in the range of between 5 and 40 fractions by volume based on after sintering. More specifically, the present invention provides a composition for preparing a fully ceramic capsulated nuclear fuel containing three-layer-structured isotropic nuclear fuel particles coated with the substance which includes, as a main ingredient, a silicon carbide derived from a precursor of the silicon carbide wherein a condition of ΔLC >ΔLm at normal pressure sintering is created, where the sintering shrinkage of the coating layer of the three-layer-structured isotropic nuclear fuel particles is ΔLC and the sintering shrinkage of the silicon carbide matrix is ΔLm; material produced therefrom; and a method for manufacturing the material. The residual porosity of the fully ceramic capsulated nuclear fuel material is 4% or less.

Classes IPC  ?

• G21C 3/62 - Combustible céramique
• G21C 3/02 - Éléments combustibles

Abrégé

A combination of a top nozzle and a guide thimble of a nuclear fuel assembly and, more particularly, a structure for joining an inner-extension tube, the top nozzle and the guide thimble. When an inner-extension tube head, which is provided as a means for facilitating removal of the top nozzle of the nuclear fuel assembly from the guide thimble, is removed from an inner-extension tube body to separate the top nozzle from the nuclear fuel assembly, the inner-extension tube body is prevented from undesirably rotating, so that the guide thimble and the inner-extension tube body can maintain the joined state.

Classes IPC  ?

• 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 3/334 - Assemblage des faisceaux

Abrégé

The present invention provides a zirconium alloy containing 1.1-1.2 wt% of niobium, 0.01-0.2 wt% of phosphorous, 0.2-0.3 wt% of iron and a remainder made up by zirconium, and a method for manufacturing a zirconium alloy having excellent corrosion resistance performance and a resistance performance against creep deformation, the method comprising: a first step of manufacturing an ingot by dissolving the mixture which constitutes the zirconium alloy; a second step of solution heat treating the ingot manufactured in the first step at 1,000-1,050°C (β-phase interval) for 30-40 minutes, then rapidly cooling same in water and β-quenching same; a third step of preheating the ingot which was heat-treated in the second step at 630-650°C for 20-30 minutes, then hot-rolling same at a reduction ratio of 60-65%; a fourth step of performing primary intermediate vacuum heat treatment on the hot-rolled material in the third step at 570-590°C for 3-4 hours, then performing primary cold-rolling on same at a reduction ratio of 30-40%; a fifth step of performing secondary intermediate vacuum heat treatment on the primarily cold-rolled material in the fourth step at 560-580°C for 2-3 hours, then performing secondary cold-rolling on same at a reduction ratio of 50-60%; a sixth step of performing tertiary intermediate vacuum heat treatment on the secondarily cold-rolled material in the fifth step at 560-580°C for 2-3 hours, then performing tertiary cold-rolling on same at a reduction ratio of 30-40%; and a seventh step of performing final vacuum heat treatment on the tertiarily cold-rolled material in the sixth step at 440-650°C for 7-9 hours.

Classes IPC  ?

• C22C 16/00 - Alliages à base de zirconium
• C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
• B21B 3/00 - Laminage des matériaux faits d'alliages particuliers dans la mesure où la nature de l'alliage exige ou permet l'emploi de méthodes ou de séquences particulières

Abrégé

The purpose of the present invention is to provide a zirconium alloy composition and a preparation method therefor, the zirconium alloy composition having excellent mechanical properties and corrosion resistance and capable of being used within a nuclear power plant reactor which gradually becomes harsher while aiming not only for high-temperature, high-pressure, and water-chemistry environments within the reactor, but also long-period, high burn-up, and load-following operations. The zirconium alloy composition for nuclear fuel, according to the present invention for achieving the purpose, comprises: 0.9-1.7 % by weight of niobium (Nb); 0.01-0.3 % by weight of stannum (Sn); 0.1-0.7 % by weight of chromium (Cr); 600-1,400 ppm of oxygen (O); and zirconium (Zr) as the remainder. Further, the method for preparing a zirconium alloy composition for nuclear fuel, according to the present invention for achieving the purpose, comprises: a step of producing an ingot by melting elements of the alloy composition (SI); a step of subjecting the ingot produced in step SI to heat treatment at a phase region temperature and rapidly cooling the ingot to room temperature (SII); a step of subjecting the ingot cooled in step SII to preheating and hot-rolling (SIII); a step of subjecting the rolled material, which has been hot-rolled in step SIII, to primary intermediate heat treatment and then to primary cold-rolling (SIV); a step of subjecting the rolled material, which has been rolled in step SIV, to secondary intermediate heat treatment and then to secondary cold-rolling (SV); a step of subjecting the rolled material, which has been rolled in step SV, to tertiary intermediate heat treatment and then to tertiary cold-rolling (SVI); and a step of subjecting the rolled material, which has been rolled in step SVI, to final heat treatment (SVII).

Classes IPC  ?

• G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages

Abrégé

The objective of the present invention is to provide a zirconium alloy composition and a manufacturing method thereof, wherein the zirconium alloy composition is capable of improving high-temperature oxidation and corrosion resistance by applying an improved manufacturing method and adjusting the contents of alloy elements such as niobium, copper, iron, and oxygen during a long-term high-burnup operation under a high-temperature and high-pressure environment in a reactor of a nuclear power plant, or in the event of a loss-of-coolant accident (LOCA) among design-based accidents. To this end, the zirconium alloy composition according to the present invention comprises: 1.1 to 2.2 wt.% of niobium (Nb); 0.01 to 0.5 wt.% of copper (Cu); 600 to 1400 ppm of oxygen (O); and zirconium (Zr) as a remainder. Also, to achieve the aforementioned objective, the manufacturing method of a zirconium alloy composition, according to the present invention, comprises: a step (S I) of producing an ingot by repeating dissolution of additive elements of the alloy composition 3 to 4 times; a step (S II) of surrounding the ingot produced in the aforementioned step (S I) with stainless steel, heat-treating the ingot for 20 to 30 minutes at ambient temperature, and then water-cooling the ingot; a step (S III) of heat-treating the ingot which has been water-cooled in the aforementioned step (S II) for 20 to 30 minutes at 600 to 650°C and then hot-rolling the ingot; steps (S IV, S V, and S VI) of intermediately heat-treating the plate which has been hot-rolled in the aforementioned step (S III) for 2 to 5 hours at 550 to 590°C and then repeating the cold-rolling of the plate 3 times; and a step (S VII) of finally heat-treating the plate which has been rolled in the step (S VI).

Classes IPC  ?

• G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
• C22C 16/00 - Alliages à base de zirconium
• C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
• C22C 1/02 - Fabrication des alliages non ferreux par fusion

Abrégé

The purpose of the present invention is to provide a zirconium alloy composition having an improved anti-corrosion characteristic which can be utilized for nuclear fuel cladding and as material for nuclear structures, and a method for producing the zirconium alloy, the optimal heat treatment conditions being considered for the zirconium alloy, wherein tin which has a negative effect on corrosion resistance is completely eliminated from the zirconium alloy, and copper is added thereto after increasing molybdenum content to greater than the solid solubility threshold level. The zirconium alloy for nuclear fuel cladding according to the present invention comprises 0.5-1.2 wt% niobium, 0.4-0.8 wt% molybdenum, 0.1-0.15 wt% copper, 0.15-0.2 wt% iron, and the remainder in zirconium, and the method for producing the zirconium alloy for nuclear fuel cladding comprises: a first step of producing an ingot by dissolving a mixture of zirconium alloy composition elements; a second step for solution heat-treating the ingot produced in the first step for 30-40 minutes at 1,000-1,050℃(β) and then β-quenching by rapidly cooling in water; a third step for heating the ingot heat-treated in the second step for 20-30 minutes at 630-650℃ and then hot-rolling at a 60-65% reduction ratio; a fourth step for a first intermediate vacuum heat treatment of the rolled material hot-rolled in the third step for 3-4 hours at 570-590℃ and then cold-rolling for the first time at 30-40% reduction ratio; a fifth step for a second intermediate vacuum heat treatment of the rolled material cold-rolled for the first time in the fourth step for 2-3 hours at 560-580℃ and then cold-rolling for the second time at 50-60% reduction ratio; a sixth step for a third intermediate vacuum heat treatment of the rolled material cold-rolled for the second time in the fifth step for 2-3 hours at 560-580℃ and then cold-rolling for the third time at a 30-40% reduction ratio; and a seventh step for the final heat treatment of the rolled material cold-rolled for the third time in the sixth step.

Classes IPC  ?

• C22C 16/00 - Alliages à base de zirconium
• C22F 1/18 - Métaux réfractaires ou à point de fusion élevé ou leurs alliages
• B21B 3/00 - Laminage des matériaux faits d'alliages particuliers dans la mesure où la nature de l'alliage exige ou permet l'emploi de méthodes ou de séquences particulières

Abrégé

A method for loading fuel pellets for manufacturing a nuclear fuel rod is provided. The method includes arranging fuel pellets in a row on a tray, aligning the fuel pellets in the row on the tray such that the fuel pellets are closely in contact with one another, obtaining a total length of the pellets in the row by measuring the fuel pellets in the row on the tray, and comparing the total length with a predetermined length. When the total length is smaller than the predetermined length by a difference greater than an average unit length of the pellet, one or more fuel pellets are added in the row until to increase the total length until the difference becomes smaller than the average unit length of the fuel pellet.

Classes IPC  ?

• B23P 21/00 - Machines pour l'assemblage de nombreuses pièces différentes destinées à composer des ensembles, avec ou sans usinage de ces pièces avant ou après leur assemblage, p. ex. à commande programmée
• B23Q 17/00 - Agencements sur les machines-outils pour indiquer ou mesurer
• B23Q 15/00 - Commande automatique ou régulation du mouvement d'avance, de la vitesse de coupe ou de la position tant de l'outil que de la pièce
• G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
• G01B 11/02 - Dispositions pour la mesure caractérisées par l'utilisation de techniques optiques pour mesurer la longueur, la largeur ou l'épaisseur
• B23P 19/00 - Machines effectuant simplement l'assemblage ou la séparation de pièces ou d'objets métalliques entre eux ou des pièces métalliques avec des pièces non métalliques, que cela entraîne ou non une certaine déformationOutils ou dispositifs à cet effet dans la mesure où ils ne sont pas prévus dans d'autres classes

Abrégé

A packing box for transporting PHWR fuel assemblies includes a rectangular planar bottom cell, middle cell, and top cell that include a bottom tray, a middle tray, and a top tray, respectively. Upper surfaces of the bottom tray and the middle tray define a plurality of first and second positioning grooves, respectively. Bottom surfaces of the middle tray and the top tray define a plurality of first and second fixing grooves, respectively, that correspond to the first and second positioning grooves, respectively. The bottom cell and middle cell have first and second locking protrusions, respectively. The bottom cell, middle cell and top cell assemble together to retain PHWR fuel assemblies between them within the positioning and fixing grooves.

Classes IPC  ?

• B65D 85/00 - Réceptacles, éléments d'emballage ou paquets spécialement adaptés à des objets ou à des matériaux particuliers

Abrégé

A joint structure between a top nozzle and a guide thimble of a nuclear fuel assembly and, more particularly, a structure for joining an inner-extension tube, the top nozzle and the guide thimble. When an inner-extension tube head, which is provided as a means for facilitating removal of the top nozzle of the nuclear fuel assembly from the guide thimble, is removed from an inner-extension tube body to separate the top nozzle from the nuclear fuel assembly, the inner-extension tube body is prevented from undesirably rotating, so that the guide thimble and the inner-extension tube body can maintain the joined state.

Classes IPC  ?

• 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

Abrégé

Disclosed herein is a joint structure between a top nozzle and a guide thimble. The joint structure includes an outer guide post, an inner-extension tube head, an inner-extension tube body, a wedge and the guide thimble. The outer guide post is provided with an external thread formed on a lower end thereof. The inner-extension tube head includes an annular retaining part formed on an upper end thereof. An internal thread is formed on a medial portion of the inner-extension tube head. An external thread is formed on each of upper and lower ends of the inner-extension tube body. A stop protrusion is provided under a lower end of the wedge. The wedge is welded to the inner-extension tube body after the top nozzle has been joined with the guide thimble. A stop protrusion receiving depression is formed in the guide thimble.

Classes IPC  ?

• G21C 15/00 - Dispositions pour le refroidissement à l'intérieur de l'enceinte sous pression contenant le cœurEmploi de réfrigérants spécifiques
• 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

Abrégé

Disclosed is a water-soluble coating composition, which is applied on the surface of fuel rods to prevent scratching of the surface of the fuel rods upon manufacturing a nuclear fuel assembly for light water reactors. This water-soluble coating composition facilitates the formation and removal of a coating film and the resulting coating film can exhibit strength and durability equivalent to those of an existing lacquer (nitrocellulose) coating film, and can thus be used as an alternative to lacquer, thereby easily removing the coating film and improving workplace safety, ultimately achieving improvements in the working environment and high workplace safety.

Classes IPC  ?

• G21C 3/06 - EnveloppesChemises
• C09D 135/02 - Homopolymères ou copolymères d'esters
• G21C 3/07 - EnveloppesChemises caractérisées par le matériau, p. ex. alliages
• G21C 21/02 - Fabrication des éléments combustibles ou surrégénérateurs à l'intérieur de gaines non-actives
• C09D 133/06 - Homopolymères ou copolymères d'esters d'esters ne contenant que du carbone, de l'hydrogène et de l'oxygène, l'atome d'oxygène faisant uniquement partie du radical carboxyle
• G21F 1/10 - Substances organiquesDispersions dans des supports organiques