222 results about "Uranous" patented technology

The invention discloses a method for one-step electrifying extraction and separation of uranium elements from sandstone uranium ores, which comprises the following steps: adjusting the pH value of an activation environment to be less than or equal to 3 by using an activation leaching agent, and converting the uranium elements in the sandstone uranium ores into uranyl with positive charges and complexes thereof; and a direct-current electric field with the voltage gradient of 0.1-2 V / cm is applied between the cathode and the anode, so that the uranium element moves towards the cathode chamber under the action of the electric field and is selectively reduced on the cathode, and the uranium element is reduced into a low-valence insoluble uranium-containing substance through electrons to be precipitated on the surface of the cathode. According to the method, uranium ions only forming positive charges and complexes of the uranium ions are activated and leached, and the uranium element directionally moves towards the cathode under the electrophysical actions of electromigration, electroosmosis and the like, so that the extraction of the uranium element in the sandstone uranium ore is realized; and meanwhile, soluble uranium is reduced and fixed on the surface of the cathode conductive plastic electrode through electrochemical actions such as reduction generated by electrons on the surface of the cathode conductive plastic electrode, so that one-step separation and purification of the uranium element are realized.

A phosphor composition includes a red phosphor material having a red decay rate and a green phosphor material having a green decay rate. The red phosphor material includes a Mn4+ doped phosphor of Formula I and a Eu3+ doped uranium phosphor, and a difference between the red decay rate and the green decay rate is no more than 7 ms, AxMFy:Mn4+ (I), wherein A is Li, Na, K, Rb, Cs, or a combination thereof; M is Si, Ge, Sn, Ti, Zr, Al, Ga, In, Sc, Hf, Y, La, Nb, Ta, Bi, Gd, or a combination thereof; x is an absolute value of a charge of the MFy ion; and y is 5, 6 or 7. A device is also provided.

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 provides a method for accurately regulating and controlling pores of an MXene material by utilizing a phosphonic acid ligand, which mainly comprises the following key steps of: directionally removing a main group element (A) layer of an MAX precursor by wet etching to obtain lamellar MXene, and then introducing a protonated quaternary amine compound intercalator to strip the MXene. And finally, carrying out functional modification and conversion by adopting a phosphonic acid ligand, and stably introducing phosphonic acid groups between layers and on the surface of MXene through solvothermal reaction to realize accurate regulation and control of interlayer spacing. The prepared material can realize efficient adsorption of uranyl in an acidic environment, shows high selectivity, high adsorption capacity and good acid stability and regeneration capacity to uranyl, provides a stable and efficient selective adsorption solution for treating high-acidity uranium-containing nuclear wastewater, and has a remarkable industrial application prospect.

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 covalent organic framework with oxidation-reduction activity and a bionic nano-channel structure as well as a preparation method and application of the covalent organic framework, and belongs to the technical field of environmental protection. According to the preparation method, 2, 4-dihydroxybenzene-1, 3, 5-tricarboxaldehyde and 2, 5-bis (allyloxy) terephthaloyl hydrazine are taken as raw materials, a two-dimensional covalent organic framework with oxidation-reduction activity is synthesized, and then a sulfonic acid group with negative charges is covalently grafted, so that a functional material with a bionic nano-channel structure is formed. The material has regular porous channels and rich functional sites, the porous channels provide efficient mass transfer paths and adsorption spaces for uranyl ions, and the functional sites realize specific recognition of the uranyl ions through oxidation-reduction reaction and electrostatic interaction, so that the material shows synergistic advantages of strong selectivity, high adsorption capacity and rapid adsorption kinetics on uranium. The method is simple and low in cost, and the prepared material is clear in structure, good in hydrophilicity, capable of efficiently adsorbing uranyl ions and good in application prospect.

The invention discloses high-urease microbial gel, a preparation method and a method for repairing uranium-polluted soil by using the high-urease microbial gel, and belongs to the technical field of environmental pollution microbial treatment. The preparation method comprises the following steps: 1) mixing sodium alginate, urea and a water-retaining agent to obtain a carrier solution; 2) uniformly mixing the high urease bacteria solution in the logarithmic phase with the carrier solution according to a volume ratio of 5-25% to obtain a bacteria solution mixture; and (3) dropwise adding the bacterial liquid mixture into a cross-linking agent which is stirred at a constant speed for cross-linking and curing, and freeze-drying to obtain the high-urease microbial gel. The high-urease microbial gel is applied to the periphery of a root system of a uranium-enriched plant planted in uranium-contaminated soil to be repaired, and uranium-contaminated soil is repaired through combination of microorganisms and plants. Urease-producing bacteria in the high-urease microbial gel induce decomposition of urea to generate carbonate, uranyl ions in the soil are activated, the mobility of uranium in the soil is improved, and extraction of uranium in the soil by uranium-enriched plants is promoted.

The invention discloses a method for improving uranium immobilization by bacillus by using an extracellular polymeric substance, and belongs to the field of environmental engineering, the bacillus licheniformis X-113 is separated from a uranium-polluted environment and is preserved in the China Center for Type Culture Collection (CCTCC) with the preservation number of CCTCC NO: M 20251207, and the bacillus licheniformis X-113 is preserved in the China Center for Type Culture Collection (CCTCC) with the preservation number of CCTCC NO: M 20251207. By optimizing the EPS culture conditions, the fixing capacity of the EPS-Bacillus sp.X-113 on uranium is remarkably enhanced compared with that of Without EPS-Bacillus sp.X-113, and the fixing capacity of the EPS-Bacillus sp.X-113 on uranium is remarkably enhanced compared with that of Without EPS-Bacillus sp.X-113. And numerous functional groups in EPS, such as carboxyl, hydroxyl, amino and the like, can be subjected to complexation, ion exchange and other reactions with uranium ions to fix the uranium ions, so that the uranium fixation of the bacillus is greatly improved.

The invention relates to the technical field of water pollution prevention and control and the technical field of new energy, and discloses an electrochemical baffle plate device and method for uranium-containing wastewater treatment and uranium recovery. The device comprises a reactor box body, the reactor box body is divided into a plurality of compartments by electric baffle plates, and each compartment is internally provided with a pair of cathode and anode electric baffle plates; and the cathode and anode electric baffle plates are respectively fixed through an electrode groove in a waterproof manner. The baffle plates divide the box body into a plurality of compartments, each compartment is divided into an upper flow chamber and a lower flow chamber, and the cathode and anode baffle plates are connected with an adjustable power supply through wires. Single-chamber dual-electrode electrochemical reaction is used as a basic unit, specific adsorption of a functionalized electrode material and an electrochemical in-situ reduction function are efficiently coupled through electrode material modification, electrode configuration design and electrode arrangement optimization, meanwhile, electrodes are embedded in a matrix mode, a diversion function is achieved, and the electrochemical in-situ reduction function is achieved. And efficient removal and resource recovery of uranium ions in the wastewater are realized.

The application provides a carbon-based material and a preparation method and application thereof, and a uranium-containing wastewater purification method, and relates to the technical field of water treatment.The carbon-based material comprises a carbon base and nano zero-valent iron particles filled in the pores of the carbon base and loaded on the surface of the carbon base.By doping the nano zero-valent iron in the carbon base and loading the nano zero-valent iron particles on the surface of the carbon base, the carbon-based material can increase the diffusion of the nano zero-valent iron particles, effectively prevent the defects of agglomeration and oxidation of the nano zero-valent iron particles, and improve the stability of the nano zero-valent iron particles in the carbon-based material.The carbon-based material is applied to the purification of uranium-containing wastewater, has excellent removal effect on uranium ions, and has no toxicity, corrosiveness and radioactivity in the recycling process of the carbon-based material, so that secondary pollution is avoided.

The invention discloses a preparation method of a vacancy coupled nano tip material for electrochemical seawater uranium extraction, which comprises the following steps: slicing foamed nickel, performing ultrasonic treatment in acetone, ethanol, pure water and a hydrochloric acid solution in sequence, thoroughly washing with pure water, and drying for later use; the preparation method comprises the following steps: dissolving a cobalt source, urea and ammonium fluoride in pure water, transferring the solution into a polytetrafluoroethylene lining, then adding treated foamed nickel, reacting in a high-pressure reactor, taking out a material, washing with pure water, and drying; and then calcining the dried flaky material, and treating with Ar plasma after calcining to obtain the vacancy-coupled nano tip material. The Co3O4 nano tip array rich in oxygen vacancies grows on the surface of the foamed nickel, an enhanced electric field on the nano tip induces OH <-> in a solution outside an electrode surface interface to be enriched, a local alkaline pH protection layer is formed, and attachment and deposition of metal salt on the surface of the electrode are reduced.

The invention discloses a device, a material and a method for efficiently extracting uranium from salt lake water flow, and particularly relates to a method for converting mechanical energy into electrochemical energy in a solid-liquid interface contact separation process of the water flow on the surface of a composite material by utilizing high-low fall flow of uranium-containing water such as salt lake water. Free uranyl ions are spontaneously reduced and deposited on a uranium collection substrate with a high specific surface area. The method effectively solves the problems caused by low efficiency, high energy consumption and use of chemical reagents in a traditional method, has good economic benefits and environmental friendliness, and is a uranium extraction strategy which is more efficient, environmentally friendly and low in cost.

The invention discloses an MXene-coated PZS-C gel structure membrane electrode as well as a preparation method and application thereof, and belongs to the technical field of electrochemical uranium removal. Carrying out etching stripping or etching intercalation stripping on the MAX powder to form an MXene nanosheet suspension; the preparation method comprises the following steps: dissolving phosphonitrilic chloride trimer and 4, 4-dihydroxy diphenyl sulfone, adding triethylamine, and carrying out condensation reaction under the ultrasonic action to obtain microspherical PZS; the preparation method comprises the following steps: stirring and mixing an MXene nanosheet suspension and microspherical PZS, depositing the mixture on a substrate in a vacuum-assisted filtration manner to form a membrane body, and carrying out vacuum freeze drying and calcination on the membrane body to obtain the MXene-coated PZS-C gel structure membrane electrode which has good stability, fully exposes active sites, is used for electrochemical separation of uranyl ions, and has a good application prospect in electrochemical separation of uranyl ions. The maximum removal amount of the material reaches up to 3375.44 mg / g and is generally higher than that of other electrochemical uranium removal materials, and the material has a good application prospect.

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.

This invention discloses a method for precipitation separation and ceramic solidification of divalent strontium and tetravalent uranium in radioactive waste liquid, relating to the field of radioactive waste liquid treatment and disposal. U in high-level radioactive waste liquid is in the form of hexavalent uranyl (UO2). 2+ U exists in the form of hydrogenation catalytic reduction, and the present invention uses hydrogenation catalytic reduction to prepare U. 4+ Sr 2+ and U 4+ ionic radius and Ln 3+ Due to the significant differences, CePO4·0.667H2O cerium phosphate, which has a stronger nuclide-containing capacity, was selected as the co-precipitation enrichment agent for Sr. 2+ and U 4+ Separation precipitant. Inexpensive raw materials such as UO2(NO3)2·6H2O, Sr(C2H3O2)2, NH4H2PO4, and Ce(NO3)3·6H2O are selected. By controlling the Sr... 2+ :U 4+ Ion ratio, reaction time, temperature, pH, and preparation of well-developed Sr crystals 2+ / U 4+ The precipitate of cerium phosphate solid solution with high solid content is avoided by using spark plasma solid-state sintering technology to prevent grain agglomeration and adhesion during high-temperature dehydration and crystal transformation of cerium phosphate. Furthermore, pressure sintering can promote further growth of nanocrystals and promote U... 4+ and Sr 2+ Homogenization within the monazite ceramic solidified body enables a one-step preparation of monazite ceramic solidified body from a lanthanite solid solution.

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 relates to a preparation method and application of a PAM / PB / PAO dual-network hydrogel adsorption material with flexibility and uranium adsorption selectivity. The invention relates to a preparation method and application of a PAM / PB / PAO dual-network hydrogel adsorption material. The technical problems that an existing hydrogel uranium adsorption material is poor in mechanical property, uneven in functional group distribution, low in adsorption selectivity in an actual complex water body and insufficient in cycling stability are solved. The method comprises the following steps: carrying out radiation crosslinking treatment to obtain PAM / PB / PAN composite hydrogel; and carrying out amidoximation reaction to obtain the PAM / PB / PAO dual-network hydrogel adsorption material. The material has excellent anti-fatigue property, high adsorption capacity and good cycle stability, and shows remarkable adsorption selectivity on uranyl ions in the presence of various competitive ions. The PAM / PB / PAO dual-network hydrogel adsorption material with flexibility and uranium adsorption selectivity prepared by the invention is applied to the field of uranium adsorption in radioactive waste liquid.

The invention discloses a preparation method of a fiber material, the fiber material and application, and belongs to the technical field of uranium extraction materials.The preparation method comprises the steps that firstly, polyguanidine is grafted to acrylic fibers through a hydrothermal method, then zwitterionic monomers with double bonds are functionalized to the surfaces of the acrylic fibers through a tert-butyl hydroperoxide surface grafting polymerization method, and the fiber material is obtained. And finally, carrying out amidoximation in a weakly alkaline hydroxylamine solution, washing and drying to obtain the double-effect anti-pollution high-efficiency uranium extraction fiber material. The fiber material is prepared by the preparation method. The fiber material is used for extracting uranium from a water body. The fiber material prepared by the invention has active and passive double-effect anti-fouling performance (namely antibacterial and anti-adhesion), and is high in adsorption rate and adsorption capacity, meanwhile, the preparation method is simple, convenient and efficient, large-scale production is easy, and the fiber material has a good market prospect in the field of extraction of uranium from seawater as a novel and efficient uranyl ion adsorption material.

The invention discloses an electro-catalysis treatment method for removing uranium-containing wastewater, and relates to the technical field of electro-catalysis, according to the electro-catalysis treatment method, an embedded sensor network is used for collecting data such as concentration, conductivity and pH value of uranyl ions U (VI) and coexisting metal ions in wastewater in real time, time sequence data are corrected through DTW, and time dimension inconsistency deviation is eliminated; based on the preprocessed data, a deep learning model combining a convolutional neural network CNN and a recurrent neural network RNN is constructed, the CNN is used for extracting spatial characteristics of ion concentration distribution, the RNN captures time dependence characteristics of dynamic changes of ions, an attention mechanism is introduced to focus key interference ions, and a characteristic matrix for priority processing is generated; according to the method, the electrocatalysis operation parameters are further optimized through the interference ion characteristics output by model prediction and the dynamic influence of the interference ion characteristics on U (VI) selective adsorption, so that the adsorption efficiency and energy consumption are balanced, and meanwhile, global optimization is performed in combination with a comprehensive objective function, so that the adsorption efficiency of uranyl ions is optimal.

The invention provides an AEM electrolytic cell for reducing uranyl, and an EE-ER system and method for recovering uranium from offshore spent fuel wastewater. The EE-ER system comprises an AEM electrolytic bath, an overflow blending tank, an acid pool, an ammonia tank, a filter press and a high-temperature calcining furnace which are sequentially connected, a cathode of the AEM electrolytic bath is ZrN / CF, an overflow water outlet of the overflow blending tank is connected with a water treatment system, and a sludge outlet of the overflow blending tank is connected with the acid pool. ZrN / CF is selected as a cathode of the AEM electrolytic cell, high-activity sites are provided to promote electrochemical deposition of uranium in the spent fuel, and 100% degradation of uranium ions can be achieved within two hours. Moreover, the whole EE-ER system realizes online and continuous treatment at a pollution source, the use of an organic solvent is avoided, the purity of the recycled uranium dioxide can exceed 98%, and the recycled uranium dioxide can be directly reused as a nuclear reactor fuel.

The invention relates to the technical field of electrochemical uranium extraction, in particular to a uranium extraction method based on electrochemical mediation FeS active site regeneration. According to the specific technical scheme, under the anaerobic condition, a nano FeS modified working electrode is prepared on a carbon-based material through in-situ deposition, and a corresponding electrochemical uranium extraction system is constructed. The system operates at room temperature and low energy consumption, and U (VI) is efficiently reduced into low-toxicity and indissolvable tetravalent uranium and enriched on the surface of an electrode through efficient adsorption and coordination effects of FeS active sites on uranyl ions and driving of cathode potential. According to the uranium extraction method of the nano FeS in-situ modified carbon cloth electrode provided by the invention, consumed FeS active sites are regenerated in situ by utilizing an electrochemical method, and the high activity and long-term stability of the electrode are maintained. The method shows high extraction capacity, high selectivity and excellent cycle performance for uranium in uranium mine wastewater and seawater, and provides a reliable way for efficient and sustainable uranium resource recovery.

The application provides an AEM electrolytic cell for reducing uranyl, an EE-ER system and method for recovering uranium in offshore spent fuel wastewater. The EE-ER system for recovering uranium in offshore spent fuel wastewater comprises an AEM electrolytic cell, an overflow distribution tank, an acid tank, an ammonia tank, a filter press and a high-temperature calcining furnace connected in sequence, wherein the cathode of the AEM electrolytic cell is ZrN / CF, the overflow outlet of the overflow distribution tank is connected with a water treatment system, and the sludge outlet of the overflow distribution tank is connected with the acid tank. The AEM electrolytic cell of the application selects ZrN / CF as the cathode, provides high active sites to promote the electrochemical deposition of uranium in spent fuel, and can achieve 100% degradation of uranium ions within two hours. Moreover, the whole EE-ER system realizes online and continuous treatment at the pollution source, avoids the use of organic solvents, and the purity of the recovered uranium dioxide can exceed 98%, which can be directly reused as nuclear reactor fuel.

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 belongs to the field of chemistry and environmental technology, and relates to a preparation method of amidoximated COFs material with adsorption and detection of uranyl bifunctional. The present invention uses 3,4-diaminobenzonitrile and 2-hydroxy-1,3,5-benzenetricarboxaldehyde as raw materials, and obtains cyanated COFs material after reaction; The cyanated COFs material is subjected to amidoximation modification to obtain amidoximated COFs material with adsorption and detection of uranyl bifunctional. The amidoximated COFs material with adsorption and detection of uranyl bifunctional prepared by post-modification has high adsorption selectivity and faster adsorption kinetics (5.11mg / g / min) for uranyl, has unique and excellent adsorption performance for hexavalent uranium, is easy to recover and recycle, and is environmentally friendly.

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 invention provides an electrochemical bipolar uranium extraction method which comprises the following steps: under the cell pressure condition of 0.1-0.9 V, carrying out electrolytic treatment on a solution containing uranium ions by adopting an anode working electrode and a cathode working electrode; wherein the anode working electrode is made of one or more of nano-copper, nano-iron, foamy copper, foamy nickel, foamy cobalt, foamy iron, iron, silver and bismuth. According to the electrochemical bipolar uranium extraction method disclosed by the invention, a specific material is adopted as an anode working electrode under the ultralow cell pressure condition of 0.1-0.9 V, and the specific material and uranium ions in the solution can be subjected to spontaneous oxidation-reduction reaction, so that the uranium ions are reduced; and meanwhile, the cathode can generate electrochemical reduction reaction of uranium ions, so that the cathode and the anode can have uranium ion extraction capacity at the same time, bipolar uranium extraction is realized, the recovery efficiency of the uranium ions is improved, and the overall reaction energy consumption is reduced.