29 results about "Uranium hexafluoride" patented technology

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.

The invention provides a recovery treatment method of fluoride slag in uranium hexafluoride preparation, belongs to the technical field of nuclear industry waste slag treatment, and solves the technical problems that a product obtained by an existing fluoride slag treatment method is high in metal impurity content and low in uranium recovery rate, secondary fluoride slag is easily generated, and the product cannot be returned to a uranium purification and conversion production line for reuse. The method comprises the following steps: at the temperature of 400-600 DEG C, contacting the fluorinated slag with excessive water vapor to carry out high-temperature hydrolysis reaction, so that UF4 and uranium intermediate fluoride in the fluorinated slag generate uranium oxides U3O8 and UO3 with the fluorine ion content of less than 1mg / g, and filtering to obtain uranium oxides; mixing uranium oxide with a nitric acid solution, dissolving and reacting to obtain a uranyl nitrate solution; the pH of the uranyl nitrate solution is adjusted to 3-4, hydrogen peroxide is added for a precipitation reaction, solid-liquid separation is conducted, and uranium peroxide solid precipitates are obtained. The method is high in uranium recovery rate, low in product impurity content and capable of returning to a uranium purification and conversion production line for reuse.

A container for storing high assay low enriched uranium hexafluoride (UF6) has a cylindrical lateral wall extending between first and second heads defining a container interior for receiving the radioactive material. A plurality of cylindrical poison rods extend in parallel through the container interior. Each of the poison rods has a neutron absorber. A plurality of access nozzles are situated within the first head and / or second head. Each of the access nozzles has a lateral wall defining a throughway that extends through the first head between an interior end region and an exterior end region. The interior end region captures and supports a respective end of a respective poison rod. The exterior end region is opened and closed via respectively detaching and attaching an end cap to thereby respectively expose and contain the respective poison rod.

An installation for the conversion of uranium hexafluoride (UF6) to uranium dioxide (UO2) comprises a hydrolysis reactor (4) for the conversion of UF6 into uranium oxyfluoride powder (UO2F2), a pyrohydrolysis furnace (6) for converting the UO2F2 powder supplied by the reactor (4) into UO2 powder, a supply device (8) comprising reagent injection ducts (10) for the injection of UF6, water vapor or H2, and a control system (16) designed to control the supply device (8) so as to supply at least one of the reagent injection ducts (10) with a neutral gas during a shut-down or start-up phase of the conversion installation.

The detection method can be used to detect the presence of uranium hexafluoride (UF6) in a gas stream (G). The detection method comprises humidifying the gas stream by circulating the gas stream (G) in contact with a sulfonated tetrafluoroethylene-based fluoropolymer copolymer, in particular Nafion, and then detecting the presence of hydrogen fluoride (HF) in the gas stream (G) by means of a sensor.

The invention relates to a uranium hexafluoride leakage monitoring method based on machine vision. The method comprises the following steps: obtaining a to-be-detected image containing leakage smoke in a uranium hexafluoride leakage environment; segmenting the to-be-detected image into a smoke image and a background image based on the image segmentation model; performing concentration estimation on the smoke concentration reflected by the smoke graph by adopting a twin neural network model; an input module of the twin neural network model is used for receiving input data composed of a smoke graph and a plurality of reference concentration sample graphs with different concentrations, and a feature extraction module comprises two sub-networks which are the same in structure and share weights and is used for extracting feature vectors of the smoke graph and the reference concentration sample graphs respectively. The output module is used for calculating the Euclidean distance between the two feature vectors, selecting the sample graph with the highest similarity with the to-be-detected smoke graph from the reference concentration sample graphs, and determining the concentration value of the smoke graph. The technical problem that the leakage concentration cannot be accurately obtained in real time in the prior art is solved.

This invention relates to the field of uranium resource technology, and more particularly to a direct reduction and conversion system for depleted uranium hexafluoride and its method of use. It includes: a liquid sodium supply unit for providing molten liquid sodium; a gaseous DUF6 supply unit for providing DUF6 that has been heated and stabilized to a gaseous state; a sodium thermal reduction reaction unit connected to both the liquid sodium supply unit and the gaseous DUF6 supply unit, wherein the liquid sodium and gaseous DUF6 react in the sodium thermal reduction reaction unit; a product separation unit connected to the sodium thermal reduction reaction unit for separating and classifying the solid products generated in the sodium thermal reduction reaction unit; and a tail gas recovery unit connected to the sodium thermal reduction reaction unit for condensing the gas discharged from the sodium thermal reduction reaction unit to obtain condensate, collecting sodium vapor and other volatile substances in the gas, purifying the gas, and discharging it after testing to ensure it meets emission standards. This method has a simple process, optimized reaction conditions, and is easier to implement.

The embodiment of the present application discloses a kind of measuring device and measuring method of fluorination rate of spent fuel short section, measuring device includes pipeline assembly, reaction vessel, first gas source, second gas source, collection device, vacuum device, switch assembly and heating furnace.Pipeline assembly includes first pipeline unit, second pipeline unit and third pipeline unit.The container body of reaction vessel is provided with reaction cavity.First gas source is communicated with reaction cavity, and first gas source is used to supply fluorine gas.Second gas source is communicated with reaction cavity, and second gas source is used to supply inert gas.Collection device is communicated with reaction cavity, and collection device includes at least one collection container, and collection container stores absorption solution, and the uranium hexafluoride flowing in the collection container can be dissolved in absorption solution.Vacuum device can be used at least to vacuumize collection device and reaction vessel.Switch assembly can be used at least to selectively communicate or close pipeline assembly.At least part of container body is arranged in heating furnace.

Described herein are methods for recovering uranium tetrafluoride (UF4) from uranium hexafluoride (UF6) by directly dissolving UF6 in ionic liquids and recovering UF4, which can be processed to obtain UO2 (s) or uranium metal.

The invention relates to application of natural uranium hexafluoride UF6 as a propellant in an electric propulsion system.

The invention discloses a device and method for treating and recycling uranium-containing fluorinated residues, the device comprises a plasma source, a reaction cavity and a material boat, plasma is generated in the plasma source and conveyed into the reaction cavity, the material boat is placed in the reaction cavity, and the uranium-containing fluorinated residues are located in the material boat. The recycling method comprises the following steps that S1, the blocky uranium-containing fluorinated residues are crushed, ground and then dried; s2, fluorine plasma is generated in the plasma source, and continuous generation of the fluorine plasma is maintained; s3, the generated fluorine plasma enters the reaction cavity and makes contact with uranium-containing fluorinated residue powder in the material boat, and uranium hexafluoride is generated; and S4, the generated uranium hexafluoride is collected. The device disclosed by the invention is compact, simple in structure and easy to operate, and effectively avoids the influence of a complex ion generation environment on a fluorination reaction process.

The invention relates to a uranium hexafluoride leakage experiment weighing and sampling device and an analysis and calculation method. The uranium hexafluoride leakage experiment weighing and sampling device comprises a monitoring chamber and weighing and sampling devices arranged on the bottom face, the side face and the top face in the monitoring chamber. The bottom surface of the monitoring chamber is parallel to the ground; and the sampling device is used for measuring the deposition and adhesion amount of the aerosol on the ground, the wall surface and the top surface. The method can be used for simulating measurement of the aerosol removal factor during uranium hexafluoride leakage, basic parameters after uranium hexafluoride leakage are obtained, and a basis is provided for nuclear and radiation safety analysis of the accident.

The invention discloses a uranium hexafluoride container automatic inspection system and method based on multi-sensor fusion, relates to the technical field of container defect detection, and solves the technical problems of low uranium hexafluoride container detection efficiency and large error. According to the technical scheme, the performance of the UF6 storage container is regularly and automatically detected through the advanced vision measurement technology assisted by remote control technologies such as a robot, the container detection efficiency and accuracy are improved, and the UF6 long-term storage safety level can be further improved. Meanwhile, a UF6 storage container high-quality detection information database is constructed, intelligent management and operation and maintenance under data driving are achieved, a scientific basis is provided for the detection period and frequency, and high-quality and intelligent development of the nuclear industry is rapidly promoted.

Method and system for detecting a uranium hexafluoride leak. The detection method allows for the detection of the presence of uranium hexafluoride (UF6) in a gas stream (G). The detection method comprises humidifying the gas stream by circulating the gas stream (G) through contact with a copolymer fluoropolymer based on sulfonate tetrafluoroethylene, in particular Nafion, and then detecting the presence of hydrogen fluoride (HF) in the gas stream (G) using a sensor. Figure for the abstract: Figure 1

The invention provides a method for preparing nuclear pure grade uranium hexafluoride, which comprises the following steps: (1) adding fluoride containing molybdenum, tungsten, vanadium, titanium, chromium and antimony and crude uranium hexafluoride of hydrogen fluoride impurities into a distillation kettle, and carrying out pressurized distillation to obtain a gaseous mixture; (2) introducing the gaseous mixture obtained in the step (1) into a calcium fluoride adsorption column, and removing hydrogen fluoride in the mixture through selective adsorption of calcium fluoride; and (3) carrying out single-tower pressurized distillation on the gaseous mixture treated in the step (2) to obtain nuclear pure grade uranium hexafluoride. The method solves the problems of low uranium hexafluoride purity, high energy consumption and high cost of the existing uranium purification conversion technology in the conversion technology of the high-impurity-content natural uranium concentrate, realizes cost reduction and efficiency improvement of uranium hexafluoride purification on the premise of ensuring that uranium hexafluoride reaches the nuclear purity grade standard, and has a wide application prospect. Rapid popularization of a dry uranium purification and conversion process is boosted, and the technical level of uranium purification and conversion in China is further improved.

The utility model belongs to the technical field of nuclear fuel processing equipment, and particularly relates to a multifunctional gripper mechanism for a uranium hexafluoride transport container full-automatic welding production line, which comprises a clamping jaw base, a plurality of connecting rods, a central positioning ring, a plurality of clamping cylinders, a plurality of sliding seats and a plurality of clamping jaws. And the central positioning ring is arranged at the central position of the clamping jaw base. And one ends of the connecting rods are uniformly connected in the circumferential direction of the central positioning ring. The other ends of the connecting rods are connected with the sliding seats in a one-to-one mode. The multiple clamping jaws are installed on the multiple sliding seats in a one-to-one mode. The clamping air cylinder is installed between the clamping jaw base and the sliding base. The two clamping air cylinders are evenly arranged on the two sides of the sliding seats, and each sliding seat is driven by the two clamping air cylinders to be opened and closed to drive the clamping jaws to move front and back. According to the utility model, the structure of the central positioning ring and the connecting rod is adopted, and the clamping cylinders are arranged around the clamping jaws, so that the problems of high manual dependence degree and unstable welding quality in the manufacturing process of the traditional uranium hexafluoride transportation container are solved.

The utility model belongs to the technical field of storage containers, and specifically relates to a container for collecting and storing uranium hexafluoride, which comprises a cylinder body. Both ends of the cylinder body are fixedly provided with end heads. The cylinder body and the two end heads together form a sealed cavity. A skirt support is fixedly installed on the outer wall of the end head. A first valve for injecting uranium hexafluoride is installed on the upper part of one end head, and a plug for sewage discharge is arranged at the lower part of the other end head. A condensation partition plate is arranged on the inner wall of the cylinder body. The condensation partition plate is arranged on the inner wall of the cylinder body, which can increase the condensation contact area between gaseous uranium hexafluoride and the cylinder body, enabling the gaseous uranium hexafluoride in each part of the cylinder body to be condensed and collected, thus improving the collection efficiency of uranium hexafluoride.

The invention relates to a sampling pipeline and method for uranium hexafluoride abundance laser spectrum on-line measurement, and the sampling pipeline comprises a gas inlet pipeline, a gas inlet flange, a parabolic mirror, a cylindrical gas chamber made of a cylindrical gas chamber wall, a gas extraction flange, a gas extraction pipeline, an optical window mirror flange and an optical window mirror. The parabolic mirror is fixedly mounted on the inner wall of the first end of the cylindrical gas chamber, and the first end of the cylindrical gas chamber is fastened on the gas inlet flange; the optical window mirror is fixedly mounted at the second end of the cylindrical gas chamber through an optical window mirror flange; the gas inlet pipeline penetrates through the gas inlet flange and the parabolic mirror and is inserted into the cylindrical gas chamber; and the air exhaust pipeline is mounted on the wall of the cylindrical gas chamber close to the second end of the cylindrical gas chamber through an air exhaust flange. According to the invention, the spatial distribution of gas molecules is regulated through the flow field, the spectral line broadening can be inhibited while the intensity of the plasma spectral line is maintained, and the isotope abundance measurement requirement is met; and the contact between corrosive gas and the device wall can be reduced to ensure the safety of the sampling pipeline.

The invention provides a device and method for preparing uranium hexafluoride based on uranium-containing molten salt, the uranium-containing molten salt contains uranium dioxide and / or triuranium octaoxide, and the device comprises a reaction cavity used for containing the uranium-containing molten salt; the gas inlet is communicated with the reaction cavity and is used for introducing fluorinated gas containing chlorine trifluoride into the reaction cavity, the chlorine trifluoride is subjected to fluorination reaction with each of uranium dioxide and / or triuranium octaoxide, and the fluorination reaction generates reaction gas containing uranium hexafluoride; the gas outlet is communicated with the reaction cavity and is used for discharging reaction gas; and the separation unit is used for separating uranium hexafluoride from the reaction gas.

This invention belongs to the field of storage container technology, specifically a vertical container for collecting and storing uranium hexafluoride (UF6). It includes a vertically placed cylindrical body with end caps fixed at both ends. The cylindrical body and the two end caps together form a sealed cavity. A material inlet pipe for injecting UF6 is connected to the upper end cap, and a sealing component for closing the material inlet pipe is provided. Multiple cylindrical baffles are fixedly connected to the inner wall of the cylindrical body, and these baffles are arranged circumferentially. This invention uses cylindrical baffles on the inner wall of the cylindrical body to increase the condensation contact area between gaseous UF6 and the cylindrical body, allowing for the condensation and collection of gaseous UF6 in all parts of the cylindrical body, thus improving the collection efficiency. Simultaneously, the vertical cylindrical body reduces the container's footprint, facilitating centralized storage in batches.

The present application relates to the technical field of reflection time-of-flight mass spectrometer measurement, in particular to a device for isotope analysis and impurity content measurement of uranium hexafluoride gas sample, which comprises a sample injector, an ionization area, a reflection mass analyzer, a microchannel plate detector, a preamplifier, a data acquisition card, a computer terminal and a tail gas treatment arranged in sequence, and can not only determine the trace impurity components in the uranium hexafluoride gas, but also quickly measure the abundance of uranium isotopes. The device has the characteristics of compact structure, high integration, safe and simple operation, and convenient carrying; modularization and localization are realized, and the device is easy to maintain; when the device is retired or the components are updated, the replacement and modification of the module are relatively simple; the device can quickly and accurately measure the isotope analysis and impurity content of the uranium hexafluoride gas sample.

A container for storing high assay low enriched uranium hexafluoride (UF6) has a cylindrical lateral wall extending between first and second heads defining a container interior for receiving the radioactive material. A plurality of cylindrical poison rods extend in parallel through the container interior. Each of the poison rods has a neutron absorber. A plurality of access nozzles are situated within the first head and / or second head. Each of the access nozzles has a lateral wall defining a throughway that extends through the first head between an interior end region and an exterior end region. The interior end region captures and supports a respective end of a respective poison rod. The exterior end region is opened and closed via respectively detaching and attaching an end cap to thereby respectively expose and contain the respective poison rod.

The embodiment of the present application discloses a kind of measuring device and measuring method of fluorination rate of uranium dioxide, measuring device includes pipeline assembly, reaction container, first gas source, second gas source, collection container, vacuum device, switch assembly and heating furnace.Pipeline assembly includes first pipeline unit, second pipeline unit and third pipeline unit.Reaction container includes container body and container end cover, container body is provided with reaction cavity and opening, reaction cavity is used to accommodate uranium dioxide.First gas source is communicated with reaction cavity, and first gas source is used to supply fluorine gas.Second gas source is communicated with reaction cavity, and second gas source is used to supply inert gas.Collection container is communicated with reaction cavity, and collection container is used to collect uranium hexafluoride.Vacuum device is arranged in third pipeline unit, and vacuum device can be used to vacuumize collection container and reaction container.Switch assembly can be used at least selectively to open or close first pipeline unit, second pipeline unit and third pipeline unit.

The invention discloses a recovery system for hydrogen fluoride and uranium hexafluoride in fluorinated tail gas, the recovery system comprises at least one set of recovery subsystem, the recovery subsystem comprises a heat exchanger, refrigeration equipment and a storage tank, to-be-treated process tail gas is introduced into the heat exchanger for heat exchange, hydrogen fluoride contained in the process tail gas is condensed into a liquid state, and uranium hexafluoride in the liquid state is recycled; uranium hexafluoride contained in the process tail gas is condensed into a solid state, the solid state is reserved in the heat exchanger, and then residual gas is output; the storage tank is positioned below the heat exchanger and is communicated with the heat exchanger through a self-flowing pipe, and the condensed liquid hydrogen fluoride flows into the storage tank; the device further comprises a heating component and a uranium hexafluoride output pipe, the heating component heats and gasifies uranium hexafluoride in the heat exchanger, and uranium hexafluoride is output through the uranium hexafluoride output pipe. According to the invention, hydrogen fluoride and uranium hexafluoride in the process tail gas can be recovered before the process tail gas enters the leaching tower to be treated, so that the production cost is saved, and meanwhile, the output of waste liquid can be greatly reduced.

The application belongs to the technical field of uranium hexafluoride container related equipment, and particularly relates to a mounting and replacing device for a uranium hexafluoride container assembly. The device is mounted on a mechanical arm and comprises a mounting fixing frame, a telescopic sleeve and a first driving mechanism. The telescopic sleeve is fixed to the front end of the mounting fixing frame. The first driving mechanism is fixed on the mounting fixing frame and drives the telescopic sleeve to rotate through a connecting rod. The top end of the telescopic sleeve is matched with a valve rod of the uranium hexafluoride container and is used for rotating the valve rod. The device can move in multiple angles along with the movement of the mechanical arm, can adapt to different replacing requirements, and thus can avoid close contact of personnel with radioactive materials and reduce the risk of nuclear pollution affecting the personnel.

A method for stabilizing and disposing of depleted uranium hexafluoride (UHF) is disclosed, applied to a UHF stabilization and disposal system. The steps are as follows: 1. Gasification of depleted UHF; 2. Hydrolysis and precipitation reaction; 3. Solid-liquid separation; 4. Post-precipitation treatment; 5. Post-filtrate treatment. The advantages of this invention are that it transforms the difficult-to-store depleted UHF into a stable uranium trioxide (UHMWCO) solid, achieving safe disposal of depleted UHF, reducing the required amount of depleted UHF containers, and lowering container disposal costs.

The invention provides a multi-element fluorinated molten salt uranium recovery device and method.The device comprises a gas pretreatment unit, a bubbling reaction unit, a product collection unit and a tail gas treatment unit which are sequentially connected through gas pipelines; by means of the device and method, a whole set of multi-element fluorinated molten salt uranium recovery and highly toxic and highly corrosive tail gas treatment can be safely and efficiently completed, and technical support and safety guarantee are provided for recovery of uranium in multi-element fluorinated waste molten salt generated in the operation process of a fourth-generation liquid thorium-based molten salt reactor. According to the device disclosed by the invention, the gas preheater, the gas distributor, the baffle plate, the two-stage cooling jacket and other corollary equipment are creatively arranged, so that full proceeding of a fluorination reaction and thorough condensation of uranium hexafluoride gas can be ensured, and the collection efficiency of uranium hexafluoride is improved to the greatest extent. In addition, by arranging a kettle cover water cooling ring, a detachable gas inlet pipe and other components, the convenience and safety of the multi-element fluorinated molten salt uranium recovery operation are further improved.

A method of disposing of uranium oxides and of disposing of metal casks that had formerly held uranium hexafluoride may include steps of: (a) receiving at least a quantity of at least one type of uranium oxide; (b) receiving at least one metal cask selected from the metal casks that was formerly housing at least some quantity of the uranium hexafluoride; (c) cutting up and / or shredding the at least one metal cask into smaller pieces; and (d) loading at least some of the quantity of the at least one type of uranium oxide and / or loading at least some of the smaller pieces into one or more human-made caverns. The one or more human-made caverns may be located within at least one deeply located geologic (rock) formation. The at least one deeply located geologic (rock) formation may be located at least 2,000 feet vertically below a terrestrial surface of the Earth.

The invention relates to a uranium hexafluoride leakage experiment removal factor measuring device and an analysis and calculation method. The uranium hexafluoride leakage experiment removal factor measuring device comprises a monitoring chamber and rotary sampling devices arranged on the bottom face, any side face and the top face of the monitoring chamber. The bottom surface of the monitoring chamber is parallel to the ground; the rotary sampling device comprises a cylindrical sampling box, a mechanical timing rotating mechanism is arranged in the cylindrical box body, an opening is formed in the top of the cylindrical box body and serves as a sampling opening, and the sampling opening deviates from the circular center of the cylindrical box body and faces the interior of the monitoring chamber. The invention designs a uranium hexafluoride leakage experiment rotary sampling device which can be conveniently installed in a uranium hexafluoride leakage release monitoring device and can be used for simulating measurement of aerosol removal factors during uranium hexafluoride leakage. By means of the calculation method, the basic parameters after uranium hexafluoride leakage are obtained, and a basis is provided for nuclear and radiation safety analysis of the type of accidents.