142 results about "Uranium" patented technology

The present application relates to the technical field of water treatment and environmental governance, and particularly relates to a nickel-strontium titanate electrode for removing uranium, a preparation method and application thereof, and the preparation method comprises the following steps: mixing a titanium source, an alcohol amine carrier and an alkaline solution to obtain a precursor solution; adding a nickel source and a strontium source into the precursor solution, performing ultrasonic treatment and hydrothermal reaction to obtain a nickel-strontium titanate material; and coating the nickel-strontium titanate material on the surface of a carbon fiber base material to obtain the nickel-strontium titanate electrode for removing uranium. Through the combination process of nickel doping, hydrothermal reaction and carbon cloth base coating, the prepared electrode forms a porous and uniformly dispersed composite structure, and meanwhile, the electrode can have optimal selectivity and removal efficiency for uranium in the range of pH 3-9. The nickel-strontium titanate electrode for removing uranium prepared by the present application is suitable for large-scale water treatment applications, and has a good application prospect in the fields of nuclear waste water and drinking water purification.

The application discloses an automatic air supplement method and device for an in-situ leaching uranium gas station and belongs to the technical field of in-situ leaching uranium. The automatic air supplement method comprises the following steps: according to the pressure of a gaseous gas sample storage tank and the injection pressure, automatically controlling the air supplement process of the gaseous gas sample storage tank, so that the pressure of the gaseous gas sample storage tank is greater than the injection pressure; and according to the injection pressure and the liquid injection pressure, automatically controlling the injection process, so that the injection pressure is greater than the liquid injection pressure. Through real-time detection of the pressure of each part of the in-situ leaching uranium gas station, the embodiment of the application realizes automatic and accurate regulation and control of the carbon dioxide system of the in-situ leaching uranium gas station, improves the efficiency and saves manpower.

This invention provides an optimized method and system for laser cleaning of product containers in uranium enrichment plants. It proposes a method for optimizing laser cleaning parameters. In the actual laser cleaning process, real-time data is input into the model to obtain the prediction results, i.e., the optimal laser cleaning parameter configuration, so as to achieve the best cleaning effect. A double wedge mirror spiral scanning method is used to achieve full coverage scanning of the inner wall of the container. The cleaning speed can reach up to 9000 mm / s, which improves the speed and efficiency of cleaning.

The invention discloses a magnesium-aluminum hydrotalcite / carbon nanotube composite material and a preparation method and application thereof, and the preparation method of the magnesium-aluminum hydrotalcite / carbon nanotube composite material comprises the following steps: S1, carrying out acid pretreatment on a carbon nanotube; and S2, preparing the magnesium-aluminum hydrotalcite / carbon nanotube composite material. Compared with the prior art, the preparation method of the magnesium-aluminum hydrotalcite / carbon nanotube composite material has the advantages that Mg (NO3) 2.6 H2O, Al (NO3) 3.9 H2O, CO (NH2) 2 and pretreated carbon nanotubes are adopted, and magnesium-aluminum hydrotalcite grows on the carbon nanotubes through a hydrothermal homogeneous precipitation method; through the synergistic effect of the carbon nanotubes and the magnesium-aluminum hydrotalcite, aggregation among nanoparticles is effectively prevented, the growth size of the particles is limited, and the magnesium-aluminum hydrotalcite / carbon nanotube composite material is good in crystallinity, small in particle size, high in specific surface area and high in adsorption performance. In a radioactive uranium element adsorption experiment, the adsorption efficiency is as high as 95.6%, and the adsorption capacity is as high as 17.32 mg / g.

The invention belongs to the nuclear industry and can be used for the production of fuel pellets from uranium-molybdenum metal powder enriched with uranium-235 to 7%, which can be used as fuel elements for nuclear reactors. The sintering of the pellets is carried out in an inert argon atmosphere at a temperature in the range of 1100°C to 1155°C, as the initial powder, a particle size of 160 μm is used, with a molybdenum content of 9.0 to 10.5 wt.%. The powder is preheated at a temperature of 500°C for 10-20 hours (in an argon medium), and then cold-pressed into pellets in a mold at a pressure of up to 950 MPa. According to another method, when preparing uranium-molybdenum pellets using a binder (plasticizer), the pellets are heated in argon from 300°C to 450°C for a duration of 2-4 hours before sintering, in order to remove the binder. The invention allows to increase the uranium content in the fuel, to reduce the heat accumulated in the core of the nuclear reactor, and to reduce the energy release in the event of a violation of the normal operating conditions of the nuclear reactor, which will improve its safety and emergency stability.

This invention provides an application of ion emitters based on covalent organic framework materials in thermal ionization mass spectrometry (TIEMS), specifically for improving the ionization efficiency of uranium during TIEMS measurements. Compared to conventional dual-band source modes in TIEMS, and ionization enhancement techniques such as graphite methods, benzene vapor carburizing methods, and graphene oxide methods, this invention significantly improves uranium ionization efficiency, facilitating the accurate measurement of ultra-trace and low-abundance uranium isotopes.

The present application relates to a kind of natural conditions under the estimation method of superuranic nuclide resuspension release source term.This application obtains the environmental characteristic parameter of the place of contaminated area, calculates the related parameter of superuranic nuclide pollution condition, calculates the surface covering layer factor of contaminated area soil, calculates the resuspension release source term of superuranic nuclide, can start from the characteristics of soil environment, nuclide characteristics, natural condition three aspects, based on the mass load theory of particulate matter, using the release flux of particulate matter in contaminated area soil and the level of radioactivity concentration in soil, the resuspension release source term of superuranic nuclide is calculated, realizes the resuspension release amount of superuranic nuclide in soil environment pollution under natural conditions is scientifically and accurately evaluated.

The invention relates to the technical field of nuclear reactor cores, and provides a reactor core adopting different hydrides for combined application, the reactor core comprises a plurality of fuel assemblies which are sequentially arranged in a zoning manner along the radial direction from the center to the periphery; part of the fuel assemblies simultaneously comprise uranium zirconium hydride fuel rods filled with uranium zirconium hydride fuel and uranium yttrium hydride fuel rods filled with uranium yttrium hydride fuel. Metal hydride fuel rods are introduced into the moderator-free reactor core, the reactor core neutron energy spectrum is slowed down, the reactor core fission reaction rate is increased, the reactor core critical mass is reduced, meanwhile, the equivalent nuclear density of uranium and hydrogen in different areas of the reactor core is adjusted in the mode that different hydride types are used in a combined mode, and reactor core power distribution is further flattened.

This invention provides a self-driven monitoring-type uranium adsorption and recovery system, belonging to the field of radioactive wastewater treatment and resource recovery technology. The system uses a proton exchange membrane (MFC) as its basic architecture, separating the anode and cathode chambers. Its core innovation lies in the biomimetic anode in the anode chamber, a three-dimensional porous conductive composite material formed by the self-assembly and freeze-drying of graphene oxide and uranium-reducing microorganisms, possessing both high-efficiency adsorption, biocatalysis, and rapid electron transfer functions. An external circuit monitoring system collects loop current / voltage signals in real time, using current decay as an early warning indicator of adsorption saturation. The uranium recovery unit removes UO2 particles from the biomimetic anode using physical or chemical methods, achieving resource recovery, and the anode is regenerable and reusable. This system integrates adsorption, in-situ reduction, self-driven monitoring, and resource recovery, solving the problems of difficult adsorbent regeneration, lagging monitoring, reliance on external energy, and complex recovery processes in existing technologies.

The application discloses a Ce2S3@Fe composite material and a preparation method and application thereof, and belongs to the technical field of radioactive wastewater treatment, and the preparation of the Ce2S3@Fe composite material comprises the following steps: under the protection of inert gas, cerium sulfide is added into a ferric iron solution, and then a sodium borohydride solution is slowly added dropwise, so that the ferric iron is reduced to zero-valent iron by using the reducing property of the sodium borohydride solution and is uniformly loaded on the surface of the cerium sulfide, thereby forming the Ce2S3@Fe composite material; and the prepared Ce2S3@Fe composite material is applied to purification of uranium-containing wastewater. 2+ The application adopts the above Ce2S3@Fe composite material, the preparation method and the application thereof, and has the advantages of convenient operation, low cost, environmental friendliness, fast reduction rate, long UO2 stabilization time, all-weather operation, simultaneous consideration of radioactive wastewater treatment and uranium resource recovery.

This application discloses a method for preparing a porous few-layer carbon nitride / mercapto-oxime-based seawater uranium extraction composite material with a multi-level structure, relating to the field of seawater uranium extraction materials. The composite material is prepared by repeatedly calcining melamine at high temperatures to obtain a porous few-layer carbon nitride material with high photocatalytic performance. Polyacrylonitrile is functionalized with mescapto-oxime to obtain a polymescapto-oxime solution. The porous few-layer carbon nitride is then uniformly dispersed in the polymescapto-oxime solution, and a sacrificial pore-forming agent, polyvinylpyrrolidone, is added to obtain a spinning solution. Finally, a one-step electrospinning technique is used to prepare a porous few-layer carbon nitride / mercapto-oxime-based seawater uranium extraction composite material with high adsorption performance. The resulting composite material exhibits excellent uranium adsorption performance and adsorption rate, is recyclable, and the preparation method is simple and environmentally friendly. The prepared composite material has excellent uranium adsorption performance and adsorption rate, is recyclable, and has broad application prospects in the field of seawater uranium extraction.

The invention belongs to the technical field of wastewater treatment and reuse, and particularly relates to a comprehensive reuse method for uranium purification rectification waste liquid. The method comprises the following steps: obtaining a rectification waste liquid diluent and alkali adjusting slurry; removing iron and aluminum impurities; complex extraction and recovery of molybdenum; purifying and recycling uranium; and recovering nitrate. By adopting the technical method disclosed by the invention, uranium, molybdenum, calcium, magnesium and the like in the uranium purification rectification waste liquid are effectively recovered. The uranium recovery rate reaches 97%, the molybdenum recovery rate reaches 98%, the calcium recovery rate reaches 95%, the magnesium recovery rate reaches 95%, almost no wastewater is discharged after treatment, and the uranium purification rectification waste liquid is turned into wealth.

The application discloses a kind of in-situ leaching uranium process in leaching agent injection control method and system, it is related to in-situ leaching uranium technical field, main purpose is to solve the matching precision of leaching agent injection parameter and injection hole ore bed characteristics is low, leading to low problem of leaching efficiency.Mainly including obtaining the real-time operation data of each branch well in target ore bed;Through the individualized liquid injection behavior model of each branch well, according to the real-time operation data, the expected leaching agent concentration space-time distribution and expected uranium leaching efficiency of corresponding branch well are simulated;According to the expected leaching agent concentration space-time distribution and the expected uranium leaching efficiency, the leaching agent injection control instruction of each branch well is generated according to concentration flow control strategy;The leaching agent injection control instruction is sent to the edge execution mechanism of corresponding branch well, to inject leaching agent into corresponding branch well by the edge execution mechanism according to the leaching agent injection control instruction.It is mainly used for controlling leaching agent injection process.

This invention discloses a method for constructing a physical field-enhanced electrochemical uranium deposition system, comprising: constructing an electrolytic cell: employing a bottom-in, top-out electrolytic cell with dimensions of 70 mm × 70 mm × 45 mm, the solution inlet located at the bottom left, and the outlet located at the bottom right, 20-43 mm from the bottom; and circulating the solution via a peristaltic pump connected to an external hose, using Co3O4@FeO x -IF is the cathode, NiO x -NF is the anode; a physical field coupling reaction is constructed: fluoride- and uranium-containing wastewater is added to the electrolytic cell, and the reaction is carried out under the conditions of a constructed physical field; the physical field is one of parallel coupling of a flow field and an electric field, or parallel coupling of a flow field and an electric field with an external magnetic field. This invention achieves effective product deposition, and a high removal rate can be achieved for fluoride- and uranium-containing wastewater systems when constructing a physical field, proving the feasibility and superiority of constructing a physical field.

The invention belongs to the technical field of in-situ leaching uranium mining, and particularly relates to a nano dissolved oxygen enhanced oxidation leaching system and method for in-situ leaching uranium mining. According to the system, the micro-nano bubble generation device is integrated on the main pipeline for in-situ leaching uranium mining, the dissolution efficiency of oxygen is improved through the micro-nano bubble technology, so that the resource leaching efficiency is improved, the conveying amount of the liquid source and the conveying amount of the gas source are controlled through the control device, and the hydraulic pressure and the air pressure of the main pipeline are collected and displayed; and the in-situ leaching uranium mining process can be monitored and controlled in real time.

This invention provides a covalent organic framework material, its preparation method, and its applications. The invention selects 1,3,6,8-tetra(4-aminophenyl)pyrene as the central building block and achieves trapped states within covalent organic frameworks (COFs) by controlling the symmetry of the active site (benzothiadiazole, BT). Compared to its centrosymmetric counterpart, by breaking the symmetry of the central BT core, the density of trapped states in COFs can be significantly reduced, and the lifetime of shallow trapped states can be extended to 1160.02 picoseconds. This allows more photogenerated electrons to participate in the photocatalytic reaction, ultimately achieving significant photocatalytic reduction of uranium (VI) (>99%). This invention elucidates for the first time the crucial role of symmetry breaking in suppressing excited-state decay in COFs, providing profound insights into how to improve the photocatalytic performance of COFs in environmental remediation.

This invention discloses a method for enhancing the uranium separation efficiency of commercial iron powder using an external field, comprising: adding commercial iron powder to a reactor containing fluorine- and uranium-containing wastewater; applying an external weak magnetic field or magneto-optical coupling; and performing uranium separation treatment on the fluorine- and uranium-containing wastewater under continuous stirring. This invention magnetizes the commercial iron powder by introducing a weak magnetic field, thereby attracting Fe... 2+ Migration disrupts the passivation layer on the surface of iron powder, promoting the reaction of U(VI) with Fe. 0 The redox reaction simultaneously strengthens the affinity between the magnetized iron powder particles and the paramagnetic O2 molecules, leading to the formation of γ-FeOOH nanosheets with a high specific surface area on the iron powder surface. The γ-FeOOH surface is rich in oxygen-containing functional groups, which achieve U(VI) separation through the bonding of -OH groups with U(VI). This invention, based on a weak magnetic field, further improves the separation efficiency of commercial iron powder for U(VI) in fluoride- and uranium-containing wastewater by coupling with an optical field.

This invention relates to the technical field of uranium-containing fluids, and more particularly to a device and method for simulating the transport of uranium-containing fluids under oxygen-deficient conditions. The reaction mechanism includes a U-shaped glass tube placed vertically, with an outlet on the top right and an inlet on the bottom left of the tube, and a rubber stopper at the top opening. A supply mechanism includes a helium cylinder located on the left side of the U-shaped glass tube, with a pressure-reducing valve installed at its outlet. The outlet of the pressure-reducing valve is connected to a filling gun, the other end of which can be quickly connected to the inlet. By laying sandstone strata inside the U-shaped glass tube and using a helium oxygen-removal method to create an oxygen-deficient atmosphere, the transport scenario of uranium-containing fluids under real geological conditions can be highly replicated. Combined with a thermal insulation jacket and temperature controller for precise temperature control, the experimental results are closer to natural geological processes, providing reliable data support for the study of uranium transport mechanisms.

The invention relates to the technical field of radioactive waste liquid treatment, in particular to a method for recycling nitric acid in uranium purification raffinate by adopting a heat pump rectification technology. According to the method, the nitric acid in the uranium purification raffinate is recovered by adopting a vacuum distillation technology, and the steam at the top of the rectifying tower is pressurized and heated by a heat pump compressor to serve as a heat source of a tower bottom reboiler and a feed preheater, so that the energy of the steam at the top of the rectifying tower is recycled, and the energy consumption of production operation is reduced. Meanwhile, the blockage of the reboiler is reduced through the arrangement of a pretreatment system, a forced circulation system and the like; and through the arrangement of the steam washing tower, the heat pump compressor is prevented from being damaged by acid steam, so that the operation stability of the whole system is improved, and the overhaul frequency is reduced.

The application discloses a mineralization treatment method of organic waste liquid, and belongs to the technical field of radioactive waste treatment. The organic waste liquid contains uranium, tributyl phosphate and diluent. The mineralization treatment method comprises the following steps: the organic waste liquid is separated through short-path molecular rectification to obtain a diluent fraction and a tributyl phosphate fraction; the tributyl phosphate fraction is reacted with alkali liquor to generate an alkaline hydrolysis product containing dibutyl phosphate salt, n-butanol, water and uranium; the n-butanol is collected through condensation reflux; and the remaining alkaline hydrolysis product is treated through two-stage oxygen-controlled incineration, so that phosphate glass and qualified flue gas are finally obtained. The mineralization treatment method has the advantages of no corrosion, short process, high-efficiency mineralization and stabilization of the waste liquid, direct disposal of the product, consideration of resource recovery and radioactive safety, and easy industrialization.

Fuel, intended to be irradiated in a fast neutron nuclear reactor, comprising grains of at least one metal selected from U, Pu or Th, the grains being compressed in a volume, the fuel being porous, the fuel being characterized in that it comprises open intergranular pores, forming an interconnected porosity, the volume fraction of porosity preferably being between 3% and 30%, more than 50% or 80% of the porosity being an open intergranular porosity,

The invention belongs to the technical field of uranium concentration, and particularly relates to a method for determining the structure of a pipeline connecting device and the pipeline connecting device. The method comprises the following steps: acquiring working parameters and a three-dimensional model of a target pipeline connecting device; the working parameters comprise the pressure intensity and the flow speed in the pipeline; performing numerical simulation by utilizing the working parameters and the three-dimensional model to obtain a particle size and speed distribution cloud picture of the target pipeline connecting device; according to the particle size and the speed distribution cloud picture, whether the target pipeline connecting device meets the pipeline design requirement or not is determined. According to the embodiment of the invention, solid impurities can be deposited in the operation process, the content of solid sediments in cascade is reduced, and the descending trend of the separation capacity of a cascade system is delayed.

To provide a ligand for collecting seawater uranium which can selectively collect uranium in seawater highly efficiently even at near 8 which is pH condition of seawater, a seawater uranium collection method using the ligand, and a method for producing a uranium raw material.SOLUTION: A ligand for collecting seawater uranium of the present invention is a ligand that selectively forms a metal complex with uranium in seawater, and collects the uranium, and is a compound expressed in the following general formula (1), ion derived from the compound, and one or more selected from the group consisting of polymers having the structures of the compound or the ion, where complex stability constant (logβ11) of the metal complex in seawater is 10 or more. [formula 1] (in general formula (1), R1 to R13 is as described in the text)SELECTED DRAWING: None

The present application belongs to grouting device, and particularly relates to a hydraulic piston sealing grouting device for sealing the bottom passage of a uranium in-situ leaching well. The hydraulic piston sealing grouting device for sealing the bottom passage of a uranium in-situ leaching well comprises a core pipe, the core pipe is a hollow tubular part, a liquid inlet is arranged on the side wall of the bottom of the core pipe, the liquid inlet makes the inside and outside of the core pipe communicate, a cylinder barrel is arranged outside the core pipe, a through hole is arranged at the bottom of the cylinder barrel, the core pipe penetrates through the through hole, a throttle nozzle is connected to the bottom of the core pipe, a tray assembly is arranged on the side wall of the core pipe, a piston is arranged at the front end of the tray assembly, and the piston is sealed with the cylinder barrel. The present application has the following remarkable effects: the sealing success rate of the device is 100% through 45 well sealing tests, the device is convenient to use, safe and reliable, and has good effects, and effectively solves the problem of cement slurry channeling in the previous grouting.

The invention relates to the technical field of photocatalytic materials, in particular to a covalent organic framework material as well as a preparation method and application thereof. The covalent organic framework material has a repeating unit with a structure as shown in a formula I. A covalent organic framework material based on a benzothiadiazole (BT) core is modified through an electron donating group-OCH3, a non-uniform p-pi conjugated system is further constructed through the synergistic effect of-F and-OCH3, the electronic structure of the COF material is accurately regulated and controlled, a built-in electric field is enhanced, exciton binding energy is reduced, and the shallow trap life is prolonged; according to the preparation method, the formation of deep electron traps and charge recombination are effectively inhibited, the photocatalytic performance is improved, a novel material with enhanced performance is provided for repairing a radioactive pollution environment, and uranium (VI) reduction can be efficiently catalyzed under an illumination condition.

The application relates to the technical field of radioactive wastewater treatment, and specifically discloses a method for deep treatment and resource collaborative recovery of associated mine radioactive wastewater, which comprises the following steps: S1: ammonium metatungstate, glucose, graphene oxide and hydrochloric acid dopamine are subjected to hydrothermal reaction and calcination to obtain a base powder; S2: the base powder is subjected to template pre-assembly and hydrolysis polycondensation with soluble uranium salt, phytic acid, cyanosilane and a silicon source under weak acid conditions to obtain pre-coated powder; S3: after elution by an acid eluent, the cyan group is converted into amidoxime under weak acid microwave conditions to obtain active powder; S4: the active powder, conductive carbon black and a binder containing polyvinylidene fluoride and carboxylated carbon nanotubes are made into a composite electrode; and S5: a three-electrode system is adopted, and uranium products are recovered through cathode reduction enrichment, anode reverse desorption and precipitation calcination. The composite electrode prepared by the application can realize deep purification of uranium-containing wastewater and efficient recovery of uranium, and the recovered uranium products are high in purity.

The utility model mainly relates to the technical field of in-situ leaching uranium mining, in particular to a wellhead sealing device of an in-situ leaching uranium mining liquid injection well. In the process of injecting the leaching solution into the ore bed, a certain pressure is generally required to be applied, so that the reliability of pipeline connection is ensured, and the leaching solution is prevented from leaking. Original screw threads are prone to being damaged in the disassembly and assembly process, and optimization and improvement are carried out on the screw thread assembly. The sealing piece 1 is mainly composed of a screw thread 2, a sealing ring 3 and a flange 4. And the thread form and the thread pitch of the screw thread 2 are matched with the well casing 7 of the liquid injection well. In the assembling process, the sealing ring 3 is installed in the sealing ring clamping groove in the sealing piece 1, then the sealing piece 1 is screwed into the liquid injection well pipe 7, the sealing gasket 6 is arranged on the flange 4 in a centering mode, the liquid injection pipeline 5 and the flange of the sealing piece 1 are aligned and fastened through a bolt, and assembling is completed. According to the device, the disassembly and assembly efficiency and the sealing performance are improved, and the damage frequency is reduced.

The application provides a continuously stable operation ammonia evaporation and uranium precipitation device and method, and relates to the technical field of uranium hydrometallurgy.The continuously stable operation ammonia evaporation and uranium precipitation device comprises ammonia evaporation equipment and multistage uranium precipitation equipment which are sequentially connected along the water flow direction.The continuously stable operation ammonia evaporation and uranium precipitation device can realize the continuous stable operation of the ammonia evaporation and uranium precipitation process, solves the problems, such as unavoidable overflow, discontinuous operation and the like, in the traditional ammonia evaporation and uranium precipitation process, and improves the stability and continuity of operation.