170 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 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 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 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 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 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 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 application provides a design method of a medical isotope reactor fuel solution, which comprises: the fuel solution comprises uranyl nitrate and nitric acid; the concentration of F ‑ ≤1mg / L, Cl ‑ ≤1mg / L, total boron equivalent ≤4.0μg / gU, Ru ion ≤0.02g / L, Cr ion ≤0.05g / L, Al ion ≤11.12g / L, and other impurities meet the requirements of GB / T 10266 standard; the concentration of acid, the concentration of uranium and the temperature of the fuel solution are controlled to control the pH value of the fuel solution; the operation power density of the fuel solution is not greater than 2.0kW / L, and a catalyst is used to prevent the fuel solution from generating precipitates during operation. The design method of the medical isotope reactor fuel solution provided by the application can realize long-term stable operation of the fuel solution, and is safe and economical.

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 preparation method of 5N-grade ultra-pure lutetium oxide, which comprises the following steps: removing thorium and uranium from a lutetium chloride solution, carrying out primary precipitation with oxalic acid, firing to obtain a primary lutetium oxide product, re-dissolving the primary lutetium oxide product with nitric acid, carrying out secondary precipitation with ammonia water, and firing to obtain the 5N-grade ultra-pure lutetium oxide. According to the method disclosed by the invention, the preparation of lutetium oxide with higher purity can be realized by combining extraction with impurity grading removal of oxalic acid-ammonia water double precipitation so as to meet quality index requirements required by application of materials with higher performance. The preparation method is high in stability, high in yield and suitable for industrial production and application.

The invention relates to bacillus licheniformis, application thereof and a method for recovering uranium ions in sewage, and belongs to the technical field of microbial environment restoration. The bacillus licheniformis is bacillus licheniformis FHY 108 and is preserved in the China Center for Type Culture Collection, and the preservation number of the bacillus licheniformis is CCTCC NO: M2025935. The surface display specific U (VI) binding protein of the bacillus licheniformis FHY 108 has a good enrichment effect on radioactive uranium (U (VI)) ions, the maximum U (VI) resistance of the bacillus licheniformis FHY 108 reaches 1000 mg / L, the maximum enrichment amount of the U (VI) is 395.6 mg / g, the concentration range of the radioactive element U (VI) ions in biological sewage treatment is widened, and the environment is protected.

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.