47results about "Reactors manufacture" patented technology

The present invention relates to a system (1) for extracting UF6 from a UF6 container placed in an autoclave (5), comprising a pump (24) having an inlet port (26) being connected to an upstream supply circuit (10, 20), the upstream supply circuit (10, 20) transporting UF6 from the autoclave to the pump (24); wherein the system further comprises a temperature- controlled subsystem (3) providing a heat supply to the pump (24) and at least a downstream portion of the upstream supply circuit (10, 20), the temperature-controlled subsystem (3) heat supply being adapted to maintain a temperature within the upstream supply circuit and the pump (24) during operation such that said temperature is above the crystallization temperature of UF6.

Described herein is a process for recovering uranium tetrafluoride (UF4) from hexafluoride uranium (UF6), the process comprising dissolving UF6 directly in an ionic liquid and recovering UF4, which can be processed to obtain UO2(s) or metallic uranium.

Fuel bundle has plurality of twisted ribbon fuel rodlets in hexagonal packing or circle packing arrangement in a core region encased in a multilayer casing. Arrangement of twisted ribbon fuel rodlets is facilitated by rodlet seating fixture with seating surface having a plurality of protrusions that form a receiving space for ends of the twisted ribbon fuel rodlets. Manufacture of the fuel bundle incorporates fiber manufacturing technologies and, optionally, infiltration of void spaces in core region by infiltrant. Twisted ribbon fuel rodlet manufacturing system has sub-systems that impart twist periodicity to extruded ribbons, inspect twisted extruded ribbons, and cut twisted extruded ribbons to length. Inspection sorts twisted ribbon fuel rodlets as well as provides feedback to adjust operation of sub-systems. The fuel bundle (and optional fuel bundle support) can be incorporated into a fuel assembly of a nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

The invention discloses a fuel assembly guide pipe plug pressing device, and belongs to the technical field of fuel assembly manufacturing. The device comprises a machining platform, bearing plates are symmetrically and fixedly connected to the top of the machining platform, a clamping moving assembly is jointly and fixedly installed on the side walls of the bearing plates, a moving limiting assembly is fixedly installed on the top of the machining platform, a controller is fixedly installed on the side wall of the machining platform, and an alarm lamp is fixedly installed on the top of the controller; according to the invention, by arranging the first electrode plate, the second electrode plate, the alarm lamp and other structures, the outer wall of the end plug, the inner wall of the guide pipe and the side wall of the pipe orifice of the guide pipe can be detected before the end plug is pressed into the guide pipe; if the outer wall of the end plug, the inner wall of the guide pipe and the side wall of the pipe opening of the guide pipe are sunken or protruded, the sliding plate can make contact with the first electrode plate or the second electrode plate, and then the alarm lamp is normally turned on to remind a worker that the end plug or the guide pipe is deformed.

The invention relates to a process for preparing a powder comprising one or more oxides selected from uranium oxide UO2, plutonium oxide PuO2 and minor actinide oxides, the minor actinides being selected from americium, neptunium and curium, comprising the steps of: a) cryogenic granulation of an aqueous solution comprising cations selected from uranium-based cations, plutonium-based cations and minor actinide-based cations; b) freeze-drying of the granules obtained in a); etc.; calcination of the granules from b). Applications: manufacture of nuclear fuels or blankets loaded with minor actinide(s).

The application belongs to the technical field of nuclear energy functional materials and advanced ceramic preparation, and discloses a preparation method of high-uniformity europium hafnate nano-powder based on a complexation-gel method. 3+ With Hf 4+ Atomic-level uniform mixing, solves the microsegregation problem existing in the traditional preparation method, reduces the synthesis temperature, and the product is free of impurities and hard agglomeration, has excellent sintering activity, and is strong in process controllability and easy to be enlarged in engineering, is suitable for the preparation of nuclear reactor neutron absorption control rod materials, and has good industrial application prospect.

The application discloses a method for optimizing process parameters of metal type nuclear fuel preparation process, collecting and arranging metal type nuclear fuel preparation process parameters and performance parameters, post-preparation performance parameters and microstructure metallographic pictures; establishing a metal type nuclear fuel solidification phase field model according to a solidification thermodynamic path under different process parameters; solving the metal type nuclear fuel solidification phase field model by using a Fourier spectrum method to obtain a phase field variable numerical solution; post-processing and visualizing the phase field variable numerical solution to generate a microstructure distribution map of the metal type nuclear fuel after solidification, and comparing and verifying the phase field model with the metal type nuclear fuel microstructure metallographic picture; calculating the post-solidification performance parameters of the metal fuel based on the microstructure distribution of the metal type nuclear fuel after solidification; taking the preparation process parameters as input and the performance parameters as output, constructing a nonlinear mapping proxy model between the metal type nuclear fuel preparation process parameters and the performance parameters; and solving the optimal preparation process parameters by using the nonlinear mapping proxy model given the target performance parameters of the metal type nuclear fuel.

This invention provides a sandwich-toughened ceramic-based fuel element and its additive manufacturing method, belonging to the field of nuclear reactor fuel technology. The element includes an outer shell and an inner shell, with an annular gap between them forming a sandwich space containing a silicon carbide whisker toughening structure. The method includes: additively manufacturing a double-layer shell, the geometry of which can be flexibly designed; preparing the sandwich toughening structure, which can be formed by injecting SiC whisker slurry into the sandwich space and solidifying it, or by generating self-grown whiskers in situ within the sandwich space through heat treatment of a Si and C raw material system; subsequently performing chemical vapor infiltration pretreatment; completing fuel loading and opening end sealing; and further performing enhanced CVI densification treatment. This invention introduces a sandwich toughening structure without significantly increasing the structural complexity of the element, effectively improving the fracture toughness, crack resistance, structural stability, and service stability of SiC-based fuel elements.

A nuclear reactor coated cladding may include a steel cladding having opposed interior and exterior surface and a coating disposed on the interior surface, wherein: the coating is a thermal and radiation resistant multilayer coating comprising: a ceramic layer in contact with the steel cladding, a metal oxide region separated from the ceramic layer by a metal layer, a metal nitride region separated from the metal oxide region by a metal layer, and the metal nitride region comprises at least two metal nitride layers, the metal oxide region comprises at least two metal oxide layers, each metal oxide layer and each metal nitride layer is separated from an adjacent layer by a metal layer, and a thickness of the metal layers in the metal nitride region is greater than a thickness of at least one of the metal layers in the metal oxide region.

A nuclear fuel assembly and a method of manufacture thereof are provided. The method comprises depositing a thermally conductive layer onto at least a portion of at least two nuclear fuel layers to create at least two at least partially coated layers. The method comprises stacking the at least two coated layers and bonding the at least two coated layers to form a nuclear fuel assembly.

The invention relates to a method for constructing an underground nuclear installation on a site (10) comprising a shaft (12) bored into the ground (14, 16) and defining a bottom (12a), at a given depth relative to the ground surface, and an opening (12b, 12b1, 12b2) located at the level of the ground surface surrounding the shaft. The method comprises the following phases: - construction of a protective slab (D1, D2; D; 230) against external aggressions on an area (Zcd) of the ground surface, referred to as the slab construction area, located next to the opening (12b, 12b1, 12b2) of the shaft, - construction of a reactor building (B1, B2) inside the shaft (12), the phases of construction of the protective slab (D1, D2; D; 230) and the reactor building (B1, B2) being carried out in parallel. Figure for the abridged version: Fig. 3

The application provides a connecting device and a connecting method for a nuclear power safety shell and an auxiliary structure. The connecting device comprises at least one set of mounting assemblies, at least one elastic extension mechanism, a support platform and a driving mechanism. The mounting assemblies are fixed to the load-bearing members of the auxiliary structure. The elastic extension mechanism comprises a cylinder, an elastic reset member and an extension pipe. The elastic reset member is installed in the inner cavity of the cylinder, and the extension pipe is axially arranged in the cylinder. The elastic reset member is elastically deformed along the cylinder in the state that the extension pipe moves axially along the cylinder. One end of the support platform is fixedly connected to the extension end of the extension pipe. The output end of the driving mechanism acts on the extension pipe. The driving mechanism is used to drive the extension pipe to retract along the cylinder, so that the support platform is stored in the storage position inside the auxiliary structure. Alternatively, the driving mechanism is used to release the constraint on the extension pipe, so that the support platform extends into the fitting gap to the working position.

The application particularly relates to a plate type element edge positioning method, comprising the following steps: step 1, obtaining images of a fuel cladding and a fuel core through X-ray imaging; step 2, establishing a coordinate system in the images to obtain the relative positions of each vertex of the fuel and each vertex of the fuel core, and establishing a reference coordinate system for cutting the fuel cladding; step 3, obtaining the coordinates of each vertex of the fuel cladding and each vertex of the fuel core in the reference coordinate system; and step 4, cutting the fuel cladding according to the coordinates of each vertex of the fuel cladding and each vertex of the fuel core in the reference coordinate system. The plate type element edge positioning method realizes the accurate positioning of the fuel core in the fuel cladding, improves the cutting accuracy, and avoids cutting into the fuel core in the fuel cladding to damage the structure of the fuel core when the fuel cladding is cut.

The embodiment of the application relates to the technical field of binary compounds of nitrogen and metal, and particularly relates to a preparation method of uranium nitride particle fuel and the uranium nitride particle fuel. The application provides a preparation method of uranium nitride particle fuel, which comprises the following steps: treating molybdenum-niobium metal powder, so that the molybdenum-niobium alloy powder is coated with a zirconium coating; preparing uranium oxide particles with uniform particle size; reacting the uranium oxide particles with ammonia to obtain uranium nitride particles; mixing the molybdenum-niobium alloy powder and the uranium nitride particles, so that the two are uniformly distributed in the obtained mixture; sintering the mixture, so that the obtained compact is formed into a dense structure; and forming the compact to obtain the uranium nitride particle fuel. The application also provides a uranium nitride particle fuel. The fuel prepared by the method of the application can improve the damage resistance of the fuel under strong radiation conditions, reduce the irradiation swelling of the fuel, ensure the low release of the fuel, and fully meet the application requirements in space nuclear reactors.

The present application belongs to the technical field of high temperature gas cooled reactor nuclear fuel element industrial production gas phase deposition coating furnace automation, and particularly relates to a device for coating furnace loading and discharging and rapid cleaning. A top cover translation mechanism is connected with a top cover grabbing and lifting mechanism. A top cover bottom surface cleaning mechanism and a special top cover for furnace cleaning are placed at a platform fixed position. An AGV trolley is automatically parked at a bottom empty area of the device. A feeding and sampling discharging mechanism is placed above the coating furnace. Graphite pieces grabbed from the coating furnace are placed in a graphite piece cleaning cabin. A brush cleaning mechanism is located around the graphite piece cleaning cabin. A fluidized pipe cleaning cabin stores hoisted fluidized pipes. The fluidized pipes are hoisted and taken out from the coating furnace. The present application solves the problem of low automation degree of coating furnace system loading and discharging and related component cleaning, and improves production efficiency and long-term use stability.

A nuclear fuel rod comprises nuclear fuel contained in a cladding, the cladding comprising a tube and two plugs, the tube extending along a central axis and having two ends, each plug being attached to a corresponding end of the tube by sealing the end of the tube. The tube is covered by a tube coating extending over the entire length of the tube from one end of the tube to the other.

This invention relates to the field of spherical nuclear fuel element molding technology, specifically to an isostatic pressing molding die and a method for preparing spherical fuel element blanks. The isostatic pressing molding die includes an isostatic pressing core ball mold for pressing the core ball and an isostatic pressing molding die for pressing the spherical fuel element blank. It consists of at least a die body and an inverted conical top cover for closing the opening of the die body. After mold closing, both the internal cavity and the external shape are spherical. The die material is one of nitrile rubber, silicone rubber, EPDM rubber, natural rubber, and polyurethane. When preparing spherical fuel element blanks using this die, nuclear fuel and matrix graphite powder are first filled into the die body of the core ball mold and stirred evenly. After mold closing, it is vacuum-sealed and isostatically pressed to obtain the core ball. Then, the core ball and matrix graphite powder in the fuel element blank mold are loaded, vacuum-sealed, and isostatically pressed to obtain the spherical fuel element blank. This invention provides convenient material loading, easy demolding, and reusability of the die, and also helps improve the isotropy and molding quality of the spherical fuel element blank.

An electrical feedthrough and a manufacturing method thereof are provided. The electrical feedthrough includes a lead pin, a housing, a glass, and an inner guide surface and / or an outer guide surface. The housing is located radially outward of the lead pin. The glass is located between the lead pin and the housing, insulating the lead pin and the housing from each other. The glass defines an axial inner heterogeneous interface with the lead pin and an axial outer heterogeneous interface with the housing. The inner guide surface defines an inner crack surface with the glass, the inner crack surface extending from an axial end surface of the glass to the axial inner heterogeneous interface. The outer guide surface defines an outer crack surface with the glass, the outer crack surface extending from the axial end surface of the glass to the axial outer heterogeneous interface. In this way, the electrical feedthrough can have better stability and durability.

A storage container for uranium oxide powder, comprising: - a rotating drum having a central axis; - an insert comprising a plurality of tubes extending in respective directions parallel to the central axis, the insert being fastened to the rotating drum and located inside the rotating drum; - neutron absorbers housed inside the tubes.

The application belongs to the technical field of high-temperature alloy materials, and relates to a preparation method of a nickel-based high-temperature alloy powder for a molten salt reactor, a preparation method of a nickel-based high-temperature alloy part and application. The method specifically comprises the following steps: step one, weighing raw materials according to ingredient allocation requirements, wherein the raw materials comprise Ni blocks, Cr blocks, Mo sheets, Fe-C intermediate alloy and Y2O3 particles, and the raw materials are pretreated; step two, sequentially performing vacuum induction melting and vacuum consumable melting on the pretreated raw materials to obtain a preformed rod; and step three, first performing degassing treatment on the preformed rod, and then performing rotating electrode atomization powdering to obtain the nickel-based high-temperature alloy powder after screening and impurity removal. The alloy powder has excellent molten salt corrosion resistance, high-temperature strength and radiation resistance, and can meet the long-term service requirements of the molten salt reactor at 700-850 DEG C.

Embodiments of a nuclear fuel element for use in various types of nuclear reactors are disclosed. One embodiment of the nuclear fuel element comprises a plurality of solid nuclear fuel particles, such as tristructural isotropic fuel particles (TRISO fuel particles), mixed in a non-solid matrix that is essentially stagnant relative to the plurality of solid nuclear fuel particles. The non-solid matrix may comprise a liquid metal, a liquid metal alloy, and a liquid salt. Various embodiments of the non-solid matrix include tin, lead, sodium, aluminum, bismuth, and alloys thereof. A method for producing a nuclear fuel and embodiments of a nuclear fuel core comprising the nuclear fuel element are also disclosed.

Insulated fuel assembly core (100) with axially arranged fuel monoliths (10) including channels (30) and having a composition including a fissionable fuel component, exhaust support plate (130), exhaust shield assembly (150), and insulation layer (120a, b). Fuel monoliths have an eccentric cylinder shape or a right circular cylinder shape with side surface keyway (70). The eccentric shape and / or a keyway (with associated alignment rod) provide alignment. Channels in the exhaust support plate are oriented so propellant gas flowing from the fuel monoliths through the exhaust support plate does not impinge the exhaust shield assembly. Insulated fuel assembly cores are manufactured by forming a tensioned fuel monolith stack mandrel assembly (400) using mandrel spacers (420) and internal tensioning components and mandrel winding an insulation layer on an outer surface of the tensioned fuel monolith stack mandrel assembly. Insulated fuel assembly cores can be incorporated into fuel assemblies of nuclear propulsion fission reactor structures (1100), for example, a nuclear thermal propulsion engine.

This invention provides a method for producing Fe-12 / 18Cr ferritic steel reinforced with an oxide dispersion, which enables improved impact resistance and hot tensile properties. [Solution] A method comprising: a) a step 100 of supplying ferritic steel Fe-12 / 18Cr powder and oxide powder; b) a step 200 of co-grinding the ferritic steel powder Fe-12 / 18Cr and oxide powder to obtain ferritic steel powder Fe-12 / 18Cr reinforced with oxide dispersion; c) a step 300 of sieving the ferritic steel powder Fe-12 / 18Cr reinforced with oxide dispersion to a predetermined initial average particle size; d) a step 400 of reprocessing the ferritic steel powder Fe-12 / 18Cr reinforced with oxide dispersion to obtain a predetermined final average particle size that is strictly smaller than the predetermined initial average particle size; and e) a step 500 of manufacturing ferritic steel Fe-12 / 18Cr reinforced with oxide dispersion.

Embodiments of the present application relate to the manufacture of fuel loaded in a non-radioactive shell, and particularly to a method for preparing a uranium-nitrogen-rhenium composite fuel pellet, comprising the following steps: S1: preparing a mixed powder of metallic uranium powder and metallic rhenium powder; S2: preparing a UNRe mixed powder using the mixed powder obtained in step S1; S3: pressing the UNRe mixed powder obtained in step S2 to obtain a composite fuel compact; and S4: reacting the composite fuel compact obtained in step S3 with a mixed gas of nitrogen and ammonia at a predetermined temperature and a predetermined vacuum degree for a predetermined time to obtain a high-density composite fuel pellet. The method for preparing a uranium-nitrogen-rhenium composite fuel pellet according to the embodiments of the present application can introduce rhenium elements into the fuel pellet, and the rhenium elements can block the reaction between the fuel pellet and the cladding material of the reactor, thereby improving the stability of the fuel pellet.

Fuel bundle has plurality of twisted ribbon fuel rodlets in hexagonal packing or circle packing arrangement in a core region encased in a multilayer casing. Arrangement of twisted ribbon fuel rodlets is facilitated by rodlet seating fixture with seating surface having a plurality of protrusions that form a receiving space for ends of the twisted ribbon fuel rodlets. Manufacture of the fuel bundle incorporates fiber manufacturing technologies and, optionally, infiltration of void spaces in core region by infiltrant. Twisted ribbon fuel rodlet manufacturing system has sub-systems that impart twist periodicity to extruded ribbons, inspect twisted extruded ribbons, and cut twisted extruded ribbons to length. Inspection sorts twisted ribbon fuel rodlets as well as provides feedback to adjust operation of sub-systems. The fuel bundle (and optional fuel bundle support) can be incorporated into a fuel assembly of a nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

A plated metal substrate and method of manufacture are provided. The method includes depositing a first layer on at least a portion of the metal substrate using physical vapor deposition to create a coated substrate. The method includes electroplating a second layer comprising chromium, a chromium alloy, or a combination thereof on at least a portion of the first layer to create the plated substrate.

Fuel bundle has plurality of twisted ribbon fuel rodlets in hexagonal packing or circle packing arrangement in a core region encased in a multilayer casing. Arrangement of twisted ribbon fuel rodlets is facilitated by rodlet seating fixture with seating surface having a plurality of protrusions that form a receiving space for ends of the twisted ribbon fuel rodlets. Manufacture of the fuel bundle incorporates fiber manufacturing technologies and, optionally, infiltration of void spaces in core region by infiltrant. Twisted ribbon fuel rodlet manufacturing system has sub-systems that impart twist periodicity to extruded ribbons, inspect twisted extruded ribbons, and cut twisted extruded ribbons to length. Inspection sorts twisted ribbon fuel rodlets as well as provides feedback to adjust operation of sub-systems. The fuel bundle (and optional fuel bundle support) can be incorporated into a fuel assembly of a nuclear propulsion fission reactor structure of, for example, a nuclear thermal propulsion engine.

This invention belongs to the field of nuclear fuel technology, specifically relating to a microstructure-controllable UN fuel pellet and its preparation method. The method involves using UO2 powder and high-purity carbon powder as raw materials, mixing and ball-milling them to prepare a mixed powder. The mixed powder is then pressed into a blank, which undergoes a carbothermic reaction under a nitrogen atmosphere. The carbothermic powder is then pressed into a blank and decarburized in a nitrogen-hydrogen mixed gas to obtain UN powder. The UN powder is then densified and sintered to obtain high-purity UN fuel pellets. During the densification and sintering process, the grain size of the UN fuel pellets is controlled by adjusting sintering parameters under vacuum conditions. This invention offers a simple preparation method that introduces no additives or additional elements, does not affect the service performance of large-grain fuel pellets, and reduces the pressure of spent fuel reprocessing.