50 results about "Uranium hexafluoride" patented technology

The invention relates to the technical field of radiation detection, in particular to a uranium hexafluoride simulation leakage system. The uranium hexafluoride simulation leakage system comprises a feeding chamber used for conveying gasified uranium hexafluoride to a monitoring chamber through a transmission pipeline; the monitoring chamber is provided with leakage simulation equipment and monitoring equipment; the leakage simulation equipment is connected with the transmission pipeline flange and is used for leaking uranium hexafluoride to a monitoring chamber; the monitoring equipment is used for monitoring the leakage condition in the monitoring chamber; the system further comprises a tail gas treatment system, a waste liquid treatment system and an air ventilation and exhaust system. According to the uranium hexafluoride simulation leakage system, leakage of uranium hexafluoride can be safely simulated, and monitoring is carried out to obtain leakage related data.

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.

An integrated system for recycling used nuclear fuel (UNF) emerging from a reactor has a decladding vessel separating fuel pellets from nuclear fuel rods via oxidation to produce a uranium compound. A

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 invention relates to the technical field of spent fuel dry post-treatment, and discloses a preparation method and application of a granular potassium fluoromagnesium adsorbent, and in the method, anhydrous potassium fluoride and anhydrous magnesium fluoride are utilized to prepare a high adsorption active site substance, namely potassium fluoromagnesium powder. Then, through a complex comprising hydrogel powder, bentonite, ethanol and water, granulation is performed by combining a rotating disc type granulator, and the strength and the porosity are improved through calcination. Finally, impurities difficult to volatilize are further removed through fluorination impurity removal, the gap and purity of the adsorbent are improved, the adsorbent with the large specific surface area, the high compressive strength and the high porosity is finally obtained, and the adsorbent has the good adsorption effect when adsorbing uranium hexafluoride.

The invention discloses a uranium hexafluoride leakage experiment device based on a polygon prism, and the device comprises the polygon prism, and the number of side edges of the polygon prism is a positive integer multiple of 8; a cavity is formed in the polygon prism; the side surface of the polygon prism comprises a particle size measurement laser emitting surface and a particle size measurement laser receiving surface; the particle size measurement laser emitting surface and the particle size measurement laser receiving surface are oppositely arranged; a laser emitting interface is also arranged on the particle size measurement laser receiving surface; a laser beam emitted by the laser emitting interface is parallel to a laser beam emitted by the particle size measurement laser emitting surface; the side surfaces of the polygon prism further comprise an observation surface and a sampling surface; the observation surface is perpendicular to the particle size measurement laser receiving surface; one end face of the polygon prism is externally connected with a uranium hexafluoride release pipeline; the uranium hexafluoride inlet is communicated with the chamber; the water vapor pipeline and the uranium hexafluoride inlet are connected to the same end face; the water vapor pipeline is communicated with the cavity.

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 utility model provides sealing protection equipment for a uranium hexafluoride transportation container. The sealing protection equipment comprises a shell and a locking assembly. The shell comprises an upper shell body and a lower shell body which are detachably connected, the upper shell body covers the lower shell body, and the upper shell body and the lower shell body are connected in a sealed mode. An upper cavity is formed in the upper shell, a lower cavity is formed in the lower shell, and the lower cavity and the upper cavity are communicated and form a containing cavity used for containing a transportation container. The locking assembly comprises an upper lock seat and a lower lock seat, the upper lock seat is arranged on the periphery of the bottom of the upper shell, and the lower lock seat is arranged on the periphery of the top of the lower shell. The upper lock seat comprises an upper lock plate, the lower lock seat comprises a lower lock groove, and / or the lower lock seat comprises a lower lock plate, and the upper lock seat comprises an upper lock groove. The transportation container is further packaged through the sealing protection equipment of the uranium hexafluoride transportation container, and the safety state of the transportation container in the transportation process is guaranteed. In addition, the upper locking plate is connected with the lower locking groove in an inserted mode, and / or the lower locking plate is connected with the upper locking groove in an inserted mode, so that the connection strength between the upper shell and the lower shell can be enhanced.

A conversion process for converting uranium hexafluoride into uranium dioxide includes the steps of hydrolysis of UF6 to uranium oxyfluoride (UO2F2) in a hydrolysis reactor (4) by reaction between gaseous UF6 and dry water vapour injected into the reactor (4), pyrohydrolysis of UO2F2 to UO2 in a pyrohydrolysis furnace (6) by reacting UO2F2 with dry steam and gaseous hydrogen (H2) injected into the furnace (6), extracting excess gas in the reactor (4) via a collecting device (50) comprising several filters (52), periodically cleaning the filters (52) by injecting a neutral gas into the filters (52) from the outside to the inside of the reactor (4) to remove powder stuck on the filters (52), and measuring the relative pressure in the reactor (4). The conversion method further includes carrying out point cleaning of the filters (52) when the relative pressure in the reactor (4) exceeds a predetermined point cleaning threshold.

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

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 shutdown or start-up phase of the conversion installation.

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.