42 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.

The invention relates to a transport assembly (1), in particular for transporting uranium hexafluoride UF6. The invention also relates to an outer container (20) for such a transport device (1). The transport assembly (1) comprises: - an inner container (10), the inner container (10) having a first inner container end wall (11), a second inner container end wall (12) opposite the first inner container end wall (11) in the longitudinal direction (X) of the inner container (10), and an inner container casing (13) extending between the first inner container end wall (11) and the second inner container end wall (12), and - a multi-part outer container (20) which receives the inner container (10), the multi-part outer container (20) having a lower shell (30) with a lower casing portion and the outer container (20) having an at least two-part upper shell (40, 50).

The present invention belongs to the technical field of physical and chemical testing in uranium enrichment plants, and particularly relates to a uranium hexafluoride secondary sampling and quantitative device and a sampling method thereof. The device comprises: a sampling bottle, a sample storage container joint, a sample injection volume control valve, a sample injection volume tube, a monitoring port, a valve, a pressure gauge joint, a pressure gauge, a quantitative container and a system joint; one end of the sample storage container joint is connected to the sampling bottle, and the other end of the sample storage container joint is connected to the sample injection volume control valve; the sample injection volume control valve and one end of the sample injection volume tube are threadedly connected via a pipe sleeve joint, and the other end of the sample injection volume tube is welded to the quantitative container; one end of the monitoring port and one end of the valve are sealed via a threaded interface; the other end of the valve is connected to a pressure gauge joint and a pressure gauge; the other end of the monitoring port is welded to the quantitative container; and one end of the system joint is welded to the quantitative container.

A reactor (1) for hydrolysis of uranium hexafluoride comprises a tubular injector (9) comprising first (11), second (13) and third (15) concentric fluid circulation ducts intended to be connected respectively with a source of UF6, a source of inert gas and a source of water vapor. The tubular injector (9) is obtained by additive manufacturing.

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 present application relates to the field of radiation detection technology, and in particular to a uranium hexafluoride simulated leakage monitoring system. The uranium hexafluoride simulated leakage monitoring system comprises: a feeding chamber, wherein the feeding chamber is provided with a test bench, and a temperature control device is provided on the test bench. The temperature control device is used to adjust the temperature of a storage container storing uranium hexafluoride through a coil so that the solid uranium hexafluoride in the storage container starts / stops gasification. The storage container is flange-connected with a transmission pipeline, and the transmission pipeline is flange-connected with a leakage simulation device in the monitoring chamber through a valve. The feeding chamber is also provided with a first air supply and exhaust filter; and a monitoring chamber, wherein the monitoring chamber is provided with a leakage simulation device, a second air supply and exhaust filter, a nitrogen injection interface, and a monitoring device. The uranium hexafluoride simulated leakage monitoring system of the present application can safely simulate the leakage of uranium hexafluoride and monitor and obtain leakage-related data.

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.

The application discloses a kind of based on the leakage experimental device of hexafluoride uranium of multi-prism, comprising: multi-prism, the number of side edge of multi-prism is the positive integer multiple of 8;Multi-prism is equipped with chamber inside;The side surface of multi-prism includes a particle size measurement laser emitting surface and a particle size measurement laser receiving surface;Particle size measurement laser emitting surface and particle size measurement laser receiving surface are oppositely arranged on particle size measurement laser receiving surface, and laser emitting interface is further provided on particle size measurement laser receiving surface, and the laser beam emitted by laser emitting interface is parallel to the laser beam emitted by particle size measurement laser emitting surface;The side surface of multi-prism further includes observation surface and sampling surface;Observation surface and particle size measurement laser receiving surface are perpendicular to each other;Hexafluoride uranium release pipeline is circumscribed on one end surface of multi-prism;Hexafluoride uranium inlet is communicated with chamber;Water vapor pipeline, water vapor pipeline is connected with hexafluoride uranium inlet on the same end surface;Water vapor pipeline is communicated with chamber.

The lean hexafluoride uranium stabilized disposal system comprises a precipitation reaction assembly, a solid-liquid separation device, a filtrate treatment assembly and a precipitation treatment assembly; the precipitation reaction assembly comprises a lean hexafluoride uranium gasification device, a first-stage stirring tank and a second-stage stirring tank; the solid-liquid separation device comprises a solid-liquid separator and a plate filter A; the filtrate treatment assembly comprises a crystallization tank, a plate filter B and a microwave dryer B; and the precipitation treatment assembly comprises a microwave dryer A, a reduction furnace and a leaching tower. The lean hexafluoride uranium with high storage difficulty is converted into the stable solid uranium trioxide octaoxide, the safe disposal of the lean hexafluoride uranium is realized, the required amount of the lean hexafluoride uranium container is reduced, and the container disposal cost is reduced.

The application provides a cleaning method and system of a uranium hexafluoride sampling container. The cleaning method is applied to a cleaning system of the uranium hexafluoride sampling container, the cleaning system comprises a heating device, a purification device and a cleaning and drying device, and the method comprises the following steps: heating the uranium hexafluoride sampling container by using the heating device according to a preset temperature and a preset heating time, so as to obtain a heated sampling container; emptying the uranium hexafluoride in the heated sampling container by using the purification device, so as to obtain a purified sampling container; soaking the purified sampling container by using the cleaning and drying device and a prepared soaking solution according to a preset soaking time, so as to obtain a soaked sampling container; and cleaning and drying the sampling container by using the cleaning and drying device, so as to obtain a usable sampling container. The application has the advantages of simple operation process, reduced labor intensity and small amount of waste liquid generated during cleaning.

The application relates to the technical field of sampling, in particular to a time-sharing sampling uranium hexafluoride mixed gas sampling system. The system comprises a first sampling device, a second sampling device and a third sampling device which are connected with a sampling pipeline through electromagnetic valves respectively, the sampling outlet of the first sampling device is connected with a first vacuum tank, the first vacuum tank is connected with a vacuum pump, a solid particle sampling membrane is arranged between the sampling inlet and the sampling outlet, the sampling outlet of the second sampling device is connected with a second vacuum tank, the second vacuum tank is connected with a vacuum pump, perfluorohexane solution is arranged between the sampling inlet and the sampling outlet, the sampling outlet of the third sampling device is connected with a third vacuum tank, the third vacuum tank is connected with a vacuum pump, hydrogen fluoride sampling powder is arranged between the sampling inlet and the sampling outlet, and a control unit is used for controlling the electromagnetic valves and the vacuum pumps in the sampling process. The uranium hexafluoride mixed gas sampling system can sample different substances in the uranium hexafluoride mixed gas in a time-sharing and fixed-point mode.

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 discovery of a method and the invention of a system for obtaining very high selectivity—and dissociation of the desired 235UF6 isotope in the Molecular Laser Isotope Separation (MLIS) process of the Uranium Hexafluoride (UF6) isotopes, in a single highly selective step, is described. The principle of the process and the concept of the invention are very simple: At temperatures below 100° K., and. preferably in the region of 60° K, nearly all the molecules of the expansion supercooled UE6 gas are in the ground state enabling the principles of the invention to be practically applied without-any ‘interference from other inherent, processes. Then the frequency of the selecting laser must be at 628.527 cm−1, or very close to it, for a three-photon absorption resonance with the [m(A2):(3V3)] sublevel of the third energy excitation state of the desired 235UF6 isotope. The fixing of the frequency of the selecting laser is the first basic step of the invention. The second basic step is to increase the pumping intensity of the selecting laser to a. level at which the—three-photon absorption resonance with the [m(A2):(3V3)]sublevel, of the desired 235UF6 isotope is established, elevating the molecules of the desired isotope 235UF6 to the third energy excitation state. This is achieved through the power broadening at the fundamental and the second energy excitation level as the pumping intensity of the selecting laser is increased and as a consequence of the proximity of these levels to ‘the pumping frequency. There is an intensity range for the selecting laser within which the molecules of the desired 235UF6 isotope can be selectively elevated to the third energy level through the establishment of a three-photon absorption resonance without disturbing the molecules of the unwanted, isotope 238UF6, leaving them unexcited. The selectively excited molecules of the desired 235UF6 isotope are then driven to dissociation through, the higher vibrational levels of the v3-vibrational mode and. the quasicontinuum of energy states, by a simultaneously applied dissociating laser whose exact intensity and optimum frequency can again be experimentally determined, or by any other dissociation or separation-process following the original excitation of the 235UF6 molecules to the ‘third energy excitation state (3v3) through three-photon resonance with the [m(A2):(3V3)] sublevel. The process is unique in that it can be applied, to the treatment and separation of the desired 235UF6 isotope from the Tails percentages of any isotope separation process. The method may also be. applicable to the SILEX system for enhancing the selectivity and efficiency of the process. The simplicity and versatility of the method enables: it to be applied to the separation of other hexafluoride isotopes or similar polyatomic molecules.

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 present invention relates to the technical field of spent fuel dry post-processing, and discloses a preparation method and application of a granular potassium fluoromagnesiumate adsorbent. In this method, anhydrous potassium fluoride and anhydrous magnesium fluoride are used to prepare a substance with high adsorption activity, namely potassium fluoromagnesiumate powder. The substance is then granulated using a composite comprising hydrogel powder, bentonite, ethanol, and water in combination with a rotary granulator, and calcined to increase strength and porosity. Finally, fluorination is used to further remove non-volatile impurities, thereby increasing the porosity and purity of the adsorbent. Ultimately, an adsorbent with a large specific surface area, high compressive strength, and high porosity is obtained. The adsorbent has a good adsorption effect when adsorbing uranium hexafluoride.

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.