101 results about "Uranous" patented technology

The invention discloses an application of a molybdenum disulfide-based piezoelectric catalytic material in a seawater uranium extraction material, and relates to the technical field of seawater uranium extraction, thiourea and sodium molybdate are used as precursors, and a MoS2 nanoflower with a specific 1T / 2H composite crystal structure is constructed through a hydrothermal synthesis technology. The method is placed in a uranyl nitrate solution, ultrasonic treatment is combined, efficient extraction of uranium can be achieved, and the method has potential application to extraction of uranium from seawater. The method is simple in process and environment-friendly, almost does not generate harmful waste in the synthesis process, does not need complex operation, and has good amplification preparation potential.

The invention discloses a nano flower-shaped covalent organic framework material as well as a preparation method, a device and application thereof, and belongs to the field of water treatment. An amino compound and an aldehyde group compound form a covalent organic framework structure with a specific flower-shaped structure under the action of a catalyst and a regulating agent, the covalent organic framework structure continues to react with a carboxyl compound, then metal is loaded, and the nano flower-shaped covalent organic framework material is obtained. Carboxyl in the carboxyl compound responds to uranium in water and does not respond to other metal ions, other interference ions are eliminated, in addition, the carboxyl compound further has sulfydryl which can fix subsequently-loaded metal ions, the loading capacity of the metal ions is improved, and the metal ions can be loaded on the surface of the metal ions in the surface of the surface of the surface of the surface of the surface of the surface of the surface of the surface of the surface of the surface of the surface of the surface of the surface. When the nano flower-shaped covalent organic framework material prepared by the method is used for treating water, uranium ions can quickly reach adsorption sites, and the material as an adsorbent is higher in stability and higher in adsorption selectivity.

The invention discloses a method for in-situ leaching mining of sandstone uranium ore, the concentration of bicarbonate radical ions in ore bed water in the sandstone uranium ore is lower than 0.5 g / L, the sandstone uranium ore comprises yttrium-containing uranium ore, and the carbonate content is 1.5%-2.5%; the ore bed water serves as a solvent, 500 mL of leaching agents with different pH values adjusted through sulfuric acid are prepared, and the concentration of hydrogen peroxide in the leaching agents is 2 g / L; and determining the maximum pH value when the uranium ore in the slice sample is corroded by using the leaching agents with different pH values, and taking the maximum pH value as a critical pH value. The leaching agent with the critical pH value is used for exploiting the sandstone uranium ore, corrosion to gangue minerals in the leaching process can be reduced, the number of formed colloids and CaSO4 precipitates is reduced, the precipitates are prevented from blocking an ore bed, in addition, the method can be used for target corrosion of the refractory uranium ore, and therefore efficient leaching is achieved.

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.

The invention belongs to the technical field of functional materials, and discloses an amidoxime-based chitosan microporous membrane adsorption material as well as a preparation method and application thereof. According to the amidoxime-based chitosan microporous membrane adsorption material, a chitosan microporous membrane is used as a matrix, and amidoxime groups are grafted on the matrix; the adsorption material has a microporous structure, the average pore size is 0.05-0.3 mu m, and the bacteriostasis rate on escherichia coli and staphylococcus aureus is not lower than 90%. The amidoxime group introduced in the invention has specific chelating ability to uranyl ions. Even in a simulated salt lake brine environment in which high-concentration competitive cations exist, the membrane adsorption material can still maintain high-selectivity adsorption on uranium, the extraction rate can reach 86% or above, and extremely high ion interference resistance is shown. The broad-spectrum antibacterial property of the chitosan base material is creatively utilized, so that the antibacterial rates of the obtained membrane adsorption material on escherichia coli and staphylococcus aureus exceed 90%.

The present application relates to the technical field of nuclear fuel cycle, and particularly relates to a method for recycling uranium fluorination wastewater. The method is as follows: adjusting the concentration ratio of bicarbonate and carbonate in the uranium conversion leaching solution, carrying out decolorization and filtration treatment to obtain a filtrate; the filtrate is subjected to uranium adsorption through a resin, and the resin adsorbed with uranium is subjected to leaching; the adsorption tail liquid is added with magnesium hydroxide slurry to adjust the pH to above 11, and then filtered, and the filtrate is adsorbed by amidoamine-based adsorption fiber; the adsorption tail liquid is added with magnesium carbonate slurry to generate magnesium fluoride and carbonate ions, and then filtered to obtain a sediment and a filtrate respectively; the filtrate is returned as a leaching agent of fluorination tail gas or is discharged after treatment; the sediment is used together with new magnesium carbonate to participate in fluorine removal reaction again, and the unreacted magnesium carbonate is used again. The present application realizes efficient recovery of uranium in the leaching solution and recycling of the leaching solution, fully utilizes the residual alkali in the returned liquid, reduces the treatment cost of fluorination tail gas, controls the radioactivity of the waste residue, and realizes radioactivity exemption of the treated sediment.

A one-step method for electrokinetic uranium extraction and separation from sandstone-type uranium deposit is provided, including: using an activating leaching agent to adjust pH of activation environment as pH≤3, converting uranium elements in sandstone-type uranium deposit into positively charged uranyl and its complexes; applying direct current (DC) electric field with voltage gradient of 0.1 V / cm to 2 V / cm between cathode and anode, and allowing the uranium elements to move toward a cathode chamber under the action of the electric field and to undergo selective reduction by receiving electrons to produce a low-valent insoluble uranium-containing substance precipitated on the cathode surface. The present invention, through activating leaching, allows the formation of positively charged uranium ions and their complexes only, and electrophysical effects such as electromigration and electroosmosis promote directional movement of uranium toward cathode, thereby achieving uranium extraction from a sandstone-type uranium deposit.

This invention discloses a poly(amylated oxime-ethyleneimine) modified foam-like mesoporous silica, its preparation, and its application, belonging to the fields of environmental energy chemistry and new materials technology. Firstly, using Pluronic P123 / mesotriene as a pore-forming / expanding agent and tetraethyl silicate as a raw material, foam-like mesoporous silica is obtained through hydrolysis, aging, high-temperature pore expansion, and calcination. After activation, epoxy-modified foam-like mesoporous silica is obtained through a silanization reaction. Subsequently, polyethyleneimine-modified foam-like mesoporous silica is prepared by reacting amino groups with epoxy groups. Then, it is reacted with acrylonitrile to obtain poly(acrylonitrile-ethyleneimine) modified foam-like mesoporous silica. Finally, it is reacted with NH2OH·HCl to obtain poly(amylated oxime-ethyleneimine) modified foam-like mesoporous silica. The poly(amylated oxime-ethyleneimine) modified foam-like mesoporous silica of this invention exhibits extremely high adsorption capacity and extremely fast adsorption rate for uranyl ions, and demonstrates high affinity, selectivity, and good reusability, making it applicable to large-scale seawater uranium extraction projects.

The invention relates to the technical field of wastewater treatment, in particular to a magnetic Fe3O4-coated UiO-66 composite material as well as a preparation method and application thereof. According to the specific technical scheme, sodium citrate dehydrate, ferric chloride hexahydrate and urea are dissolved in water at the room temperature, polyacrylamide is added for ultrasonic treatment, UiO-66 is added for continuous ultrasonic treatment, then a reaction is conducted at the high temperature, after the reaction is completed, an obtained product is recovered through magnetic separation, and the recovered sample is washed and dried to obtain the iron-based composite material. And the magnetic Fe3O4 and UiO-66 composite material is obtained. Through research and development of the Fe3O4-coated UiO-66 composite material, an effective scheme integrating the advantages of excellent adsorption capacity and convenient separation is provided for solving the problem of remediation of radioactive uranium pollution in water.

The application belongs to the field of hydrometallurgy, and an embodiment provides a method for selectively extracting uranium from a high-concentration sulfuric acid medium. The method comprises the following steps: providing an extraction organic phase, wherein the extraction organic phase comprises a compound and a diluent; mixing and extracting the extraction organic phase and a solution, wherein the solution comprises uranium and acid, and the sulfuric acid concentration of the solution is at least 1 g / L, wherein the compound has a structure shown in formula I; formula I, R1, R2 and R3 are independently selected from any one of C3-C18 linear, branched or cyclic aliphatic hydrocarbon groups and C6-C18 aromatic groups; and the diluent comprises at least one of sulfonated kerosene, aviation kerosene, n-hexane and cyclohexane. The method of the embodiment of the application is simple and easy to implement, and can efficiently separate uranium from coexisting impurity metal ions.

The invention provides a phosphate covalent organic framework material and a preparation method and application thereof, and relates to the technical field of adsorption materials, the phosphate covalent organic framework material has a chemical structural formula as shown in formula (I), and the phosphate covalent organic framework material is stable in carbon-carbon double bond connection. The preparation method effectively retains a P = O functional group for specifically recognizing uranyl ions, has the advantages of high adsorption capacity, good selectivity, high stability and the like, overcomes potential safety hazards and material stability defects of a traditional solvothermal method, and provides a safe, efficient and recyclable solution for extraction of uranium from seawater.

The invention discloses a filtering and recycling method and system for concentrated slurry of uranyl carbonate and ammonium diuranate in crystallization mother liquor, and relates to the technical field of uranium purification, the recycling method comprises the following steps: S1, adopting at least two solid-liquid separation devices which are arranged in parallel to carry out alternate circulating filtering treatment on tower bottoms of crystallization mother liquor containing uranyl carbonate and / or ammonium diuranate, filtering to obtain filtered clear liquid and an ammonia-containing filter cake; s2, carrying out air stripping treatment on the ammonia-containing filter cake obtained in S1 to separate ammonia-containing gas and obtain a solid material with low ammonia content; s3, carrying out absorption treatment on the ammonia-containing gas separated in S2 to obtain an ammonium-containing product; and S4, carrying out pyrolysis treatment on the solid material with low ammonia content obtained in S2 to obtain a uranium-containing product. Through cooperation of double-machine alternate circulating filtration, air stripping separation, absorption recovery and pyrolysis conversion, the technical problems of ammonia nitrogen pollution transfer, dependence on manual operation, long flow and high water content of a filter cake are solved.

The invention belongs to the technical field of sewage treatment, and relates to a method for rapidly and synchronously removing and recycling polycyclic aromatic hydrocarbon and uranium ions in a water body and a carbon-based adsorbent, the method comprises the following steps: preparing a modified carbon-based adsorbent, activating pretreated high-density activated carbon with HPO or ZnCl, and then adding the modified carbon-based adsorbent into the activated carbon; the adsorbent is mainly composed of a large number of long-strip-shaped gap mesopores which are communicated with one another and are approximately distributed in parallel, and is assisted by a small number of discrete irregular groove mesopores, and has double functional sites; treating the polluted wastewater, and adding the adsorbent into the wastewater containing polycyclic aromatic hydrocarbon and uranium ions for adsorption; pollutants are recovered, an adsorbent is regenerated, polycyclic aromatic hydrocarbon is recovered through solvent desorption, uranium ions are recovered through NaHCOdesorption, and the adsorbent is regenerated after being washed and dried. The prepared adsorbent has double functional sites, can synchronously remove polycyclic aromatic hydrocarbon and uranium ions, and is high in adsorption speed, recyclable, environment-friendly in recovery method, low in cost and easy to industrially popularize.

The invention discloses a uranium ore leaching method and a uranium ore leaching device, and relates to the technical field of hydrometallurgy. The invention provides a novel multifunctional uranium leaching system which is characterized in that porous electrode plates and conductive liquid injection pipes are arranged at the two ends of a horizontal rotary reaction cabin, contact electrification is realized by means of an anode wire and a cathode wire, and a uranium trapping net in the horizontal rotary reaction cabin is filled with ion exchange resin; uranyl ions are enriched on the ion exchange resin under the action of an electric field. The uranium ore structure is destroyed through mechanical force, reaction sites are exposed, uranium element oxidation and dissolution are promoted through advanced oxidation, uranyl ion migration is promoted through an electric field, the advanced oxidation reaction efficiency is improved, uranyl ions driven by the electric field are adsorbed through ion exchange resin in real time, and the three forms a synergistic strengthening effect. The acid consumption is obviously reduced; and the leaching efficiency and the recovery rate of uranium are improved.

This invention discloses a polyphosphazene / MXene self-supporting electrode loaded with cobalt single atoms, its preparation method, and its application, belonging to the field of seawater uranium extraction technology. Ti3AlC2 powder is etched in an HCl-LiF mixed solution and then ultrasonically exfoliated to obtain Ti3C2T. x Nanosheet suspension; simultaneously, hexachlorocyclotriphosphazene, 4,4'-dihydroxydiphenyl sulfone, and cobalt salt were dissolved in a solvent, and triethylamine was added. A condensation reaction was then carried out under ultrasonication to obtain Co-PZS; then Ti3C2T x After the nanosheet suspension is uniformly mixed with Co-PZS and carbon fiber fabric, it is transferred to a hydrothermal reactor for hydrothermal reaction. The resulting hydrothermal reaction product is then dried and calcined to obtain a polyphosphazene / MXene self-supporting electrode loaded with cobalt single atoms. This electrode is used for the electrochemical adsorption of uranyl ions in the solution system and exhibits excellent comprehensive uranium extraction performance, with advantages such as high capacity, fast rate, strong selectivity, and good stability, meeting the application requirements of seawater uranium extraction.

This invention relates to the field of environmental radiochemistry, specifically to an ultrasonic atomization microdroplet uranium extraction method. The specific technical solution involves adding uranium-containing wastewater and / or seawater to a uranium extraction reactor, controlling the frequency of the ultrasonic atomizing plate in the reactor to be 1.5MHz-3MHz, and reacting under different atmospheres and light sources. This invention directly utilizes oxygen from the air, water in the solution, and U(VI) as starting reactants, catalyzing the ionization of free U(VI) to obtain stable clinomic acid (UO2)4O(OH)6·5H2O under catalyst-free conditions and at room temperature and pressure, facilitating separation and enrichment from the solution. This invention utilizes the photochemical properties of U(VI) ions to achieve catalyst-free solidification of free U(VI) through a free radical-mediated reaction via microdroplets. The ultrasonic atomization microdroplet uranium extraction method of this invention has broad application scenarios in both seawater and uranium-containing wastewater.

The invention belongs to the technical field of uranium compounds, and particularly relates to a preparation method of high-purity uranyl nitrate. According to the method, the high-purity uranyl nitrate hexahydrate and uranyl nitrate trihydrate are continuously prepared by taking a ternary system phase diagram as guidance and combining a pH controlled micro-disturbance impurity removal technology and a mother liquor closed-loop circulation technology. In-situ selective removal of amphoteric impurities is achieved through accurate pH oscillation impurity removal, the impurity removal effect is enhanced in cooperation with thermal-state filtration, a target crystal phase is directionally separated out through regulation and control of a phase diagram, mother liquor after centrifugation can be directly reused for a dissolution procedure through split-flow compounding, and therefore full utilization of materials is achieved; and environmental pressure and resource waste caused by discharge of high-acidity waste liquid are avoided. The method provided by the invention ensures high purity of the product and crystal phase stability, realizes flow simplification, high-efficiency utilization of materials and zero wastewater discharge, reduces the comprehensive production cost, has good industrial suitability, and can meet the preparation requirements of high-purity raw materials such as nuclear fuel grade and the like.

The invention belongs to the technical field of environmental engineering and material science, and particularly relates to a hydroxyl-containing zinc zeolite imidazole framework material as well as a preparation method and application thereof. The preparation method comprises the following steps: mixing a zinc precursor and an imidazole ligand in proportion by adopting a mechanochemical method, mechanically grinding under the assistance of a small amount of water, washing and drying. The obtained material is of a microporous structure, the specific surface area is 500-2000 m < 2 > / g, the particle size is 20 nm-50 [mu] m, and the defect rate is high. The method has the advantages that the preparation process is green, environment-friendly, rapid, efficient and suitable for mass production, and the coordination capability can be enhanced through the synergistic effect of hydroxyl and imidazole groups of the residual raw materials. The obtained material can be used for heavy metal ion adsorption, especially has high removal rate and high adsorption capacity (50-600 mg / g) for radioactive uranium elements, and has wide application prospects in the field of environmental restoration.

The invention discloses a preparation method of a phosphoric acid amide modified carbon nitride material for treating uranium-containing wastewater. The method comprises the following steps: 1, calcining dicyandiamide at high temperature, cooling and grinding to obtain blocky carbon nitride; 2, thermally stripping the blocky carbon nitride, and performing thermal treatment under ammonia gas to obtain flaky carbon nitride with amino on the edge; 3, carrying out gas-solid phase reaction on the flaky carbon nitride and sodium hypophosphite, and then carrying out annealing treatment to obtain a phosphoric acid amide modified carbon nitride material; a phosphoric acid amide group is introduced into a framework of the material to form an intramolecular dipole structure; the material is used as a photocatalyst to be added into uranium-containing wastewater for photocatalytic reaction. The functional photocatalyst with strong intramolecular polarity is constructed by accurately introducing a phosphoric acid amide group into a carbon nitride skeleton, has strong adsorption and efficient photocatalytic reduction capabilities on uranyl ions, and can efficiently and stably treat hexavalent uranium in uranium-containing wastewater into tetravalent uranium in an open water system without a sacrificial agent; the method is suitable for uranium-containing wastewater field.

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 invention belongs to the technical field of material preparation and environmental governance, and particularly relates to a preparation method and application of MXene / polyamidoxime composite aerogel. The MXene / polyamidoxime composite aerogel with a three-dimensional hierarchical porous structure is prepared by taking an MXene dispersion liquid and an amidoxime precursor solution as reactants under the action of an initiator and hydroxylamine hydrochloride, the material can be applied to the fields of uranium-containing wastewater treatment, toxic agent polluted environment remediation and the like, good performance is kept under different humidity conditions, and the MXene / polyamidoxime composite aerogel can be applied to the fields of uranium-containing wastewater treatment, toxic agent polluted environment remediation and the like. The adsorbent can work normally in different air pressure environments, has excellent environmental adaptability, and has high adsorption capacity and adsorption rate to uranyl ions and toxic agent mimics.

A method for preparing, in the internal volume of at least one channel, a monolithic support on which uranyl cations are immobilised. The method comprises: (a) activating the inner surface of the channel(s); (b) introducing, into the internal volume of the channel(s), a polymerisation solution comprising: a monomer comprising a phosphate group, at least one crosslinking agent, several solvents, and a radical polymerisation initiator; (c) polymerising the polymerisation solution; (d) rinsing the monolithic support obtained in step (c); and (e) contacting the monolithic support previously rinsed, with a solution comprising uranyl cations. A method for capturing proteins that selectively bind uranium by means of a monolithic support prepared by the above-mentioned method, as well as to a method for recovering proteins that selectively bind uranium with the capture method.

The invention discloses a direct mass spectrometry device and method for trace uranium in a water body, and relates to the technical field of analys.The method comprises the steps that a gel film is soaked in uranium-containing wastewater and taken out, a tip is cut out, and the uranium-adsorbed gel film is obtained; dropwise adding an extracting agent on the gel film, and then applying high voltage on the gel film, so that uranium adsorbed on the gel film is extracted and moves towards the tip along with the solvent to form spray; uranium is ionized in the form of uranyl acetate and detected by a mass spectrum detection system; according to the invention, accurate analysis of trace uranium can be realized, and mass loss of uranium in a water sample due to links such as sample treatment and preservation is avoided. The device can be applied to various complex water environments, and direct mass spectrometry can be realized only by shearing gel into a triangular shape with a tip and applying voltage and an extracting agent during analysis. And the method has the advantages of high analysis speed, good linear relationship, low detection limit and the like.

The invention discloses a method for extracting trace radium in uranium tailings. The method comprises the steps of tailings pretreatment, leaching, coprecipitation, dissolution and separation. According to the method, the characteristic that phosphate is difficult to dissolve is utilized, ions such as UO2 < 2 + >, Fe < 3 + >, Al < 3 + >, Ca < 2 + > and Ba < 2 + > existing in the uranium tailing leaching solution and Ra < 2 + > generate phosphate precipitates, synchronous enrichment of radium is achieved, after the radium is dissolved through diluted hydrochloric acid, the coexisting ions are separated and removed by utilizing the property difference between the coexisting ions and the Ra < 2 + >, and the radium-containing solution is obtained through purification. Compared with the prior art, the method has the advantages that the carbonate conversion step of sulfate is omitted, so that CO2 aerosol and radium-containing aerosol pollution generated by carbonate conversion is eliminated; the separation process time is shortened, and the operation difficulty is greatly reduced; barium ions are not additionally introduced in the whole process, and competitive ions similar to radium in property are greatly reduced; and the recovery rate of radium is improved by optimizing the leaching process.

The invention relates to the technical field of uranium-containing wastewater treatment, in particular to a visible light catalytic material for efficiently reducing hexavalent uranyl ions as well as a preparation method and application of the visible light catalytic material. When hexavalent uranyl ions in wastewater are reduced by a conventional photocatalysis method, organic matters such as methanol, ethanol and the like need to be additionally added as sacrificial agents, so that the treatment cost is increased, and new pollutants are easily introduced. In order to solve the problems, the invention provides the visible light catalytic material for efficiently reducing the hexavalent uranyl ions, Fe < 2 + > is adsorbed on the surface of BiOBr in a solution through electrostatic interaction, then Fe < 2 + > and S < 2-> are subjected to a co-precipitation reaction on the surface of BiOBr, and finally, a target product BiOBr / FeS can be obtained after room-temperature aging. According to the visible light catalytic material, no sacrificial agent needs to be added in the process of reducing the hexavalent uranyl ions, compounding of electron-hole pairs can be effectively inhibited by means of the unique structure and performance of the visible light catalytic material, and the treatment cost is remarkably reduced while efficient reduction of the hexavalent uranyl ions is guaranteed.

The application discloses a separation method and a separation device for nuclide deep treatment. 12 The nanoparticles are dispersed on the surface of the ZIS nanoflower, and a CsPMo 12 / ZIS composite photocatalyst with an S-type heterojunction is successfully constructed, and then is added into nuclide waste liquid to perform a photocatalytic reduction reaction in a photocatalytic separation device. 12 In the photocatalytic process, the S-type heterojunction of the prepared CsPMo / ZIS composite photocatalyst has a strong built-in electric field driving force and a close interface contact, which is beneficial to realize efficient interface charge separation and transfer, provides a strong driving force for the generation of active species ·H, realizes efficient enrichment and separation of uranium in a high-concentration uranyl carbonate solution, and provides a new idea for efficient photocatalytic reduction of uranyl carbonate.

This invention discloses a leaching method and apparatus for uranium ore, relating to the field of hydrometallurgical technology. The invention provides a novel multifunctional uranium leaching system. Porous electrode plates and conductive injection pipes are installed at both ends of a horizontal rotating reaction chamber. Contact and energization are achieved via anode and cathode wires. An ion exchange resin is filled in a uranium trapping net within the horizontal rotating reaction chamber. Under the influence of an electric field, uranyl ions are enriched on the ion exchange resin. Mechanical force disrupts the uranium ore structure and exposes reaction sites; advanced oxidation promotes the oxidation and dissolution of uranium; the electric field promotes the migration of uranyl ions and enhances the efficiency of the advanced oxidation reaction; and the ion exchange resin adsorbs uranyl ions driven by the electric field in real time. These three factors create a synergistic enhancement effect, significantly reducing acid consumption and improving uranium leaching efficiency and recovery rate.

The invention relates to the technical field of radioactive wastewater treatment materials, in particular to an electrode material for radioactive wastewater treatment and a preparation method thereof.The electrode material comprises foamed nickel and a compound of a heterojunction material and an oxygen absorption material, the compound is loaded on the foamed nickel in situ, the heterojunction material is g-C3N4-CuO, and the oxygen absorption material is Pr2CuO4; the preparation method comprises the following steps: dissolving nitrates corresponding to Pr and Cu in a mixed solvent of water and ethylene glycol, adding citric acid, and adjusting the pH value to 5-6; carrying out heat treatment at 80-90 DEG C for 10-15 hours, adding g-C3N4 and urea, adjusting the pH value to 9-10, and putting foamed nickel; calcining at the temperature of 280-320 DEG C in an Ar / H2 atmosphere, and then calcining in air at the temperature of 380-450 DEG C; when the method is used for treating the low-concentration uranium-containing radioactive wastewater, the removal effect of over 50 percent can be achieved within 11 hours at the soonest, and the treatment time can be remarkably shortened.

This invention discloses a Ni 0 / Fe 0 This invention relates to zinc sulfide-loaded composite materials, their preparation methods, and applications, belonging to the field of environmental functional nanomaterials. The preparation method includes: dissolving zinc and sulfur precursors in a solvent to obtain ZnS nanosheets via a hydrothermal method; dispersing ZnS, iron, and nickel precursors in deionized water to form a mixed dispersion under an inert atmosphere; and adding sodium borohydride solution dropwise to the mixed dispersion to allow Ni to... 2+ and Fe 2+ In-situ reduction was performed on the zinc sulfide surface; after the reaction was completed, Ni was obtained through solid-liquid separation, washing, and freeze-drying. 0 / Fe 0 -ZnS composite material. This material can reduce Ni 0 and Fe 0 The aggregation of particles increases the exposure of surface active sites, and through the sulfur sites on the ZnS surface, the reduction activity of zero-valent metals and the bimetallic electron transfer effect, it can achieve the adsorption, reduction and fixation of uranium and selenium pollutants, which is suitable for the treatment of selenium-containing water bodies and water bodies with uranium and selenium coexistence.