A nickel strontium titanate electrode for removing uranium and a preparation method and application thereof

Abstract

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

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of water treatment and environmental governance, in particular to a nickel strontium titanate electrode for removing uranium and a preparation method and application thereof. BACKGROUND

[0002] Uranium is a radioactive metal that exists widely in nature and is discharged in large quantities in industrial activities such as mineral exploitation and nuclear energy production. Due to its long half-life and strong radioactivity, the accumulation of uranium in water bodies can have a serious impact on the ecological environment and human health. Especially in the discharge of nuclear wastewater and the treatment of mine wastewater, the concentration of uranium often exceeds the environmental standard, causing long-term pollution of water sources. Existing uranium removal technologies, such as chemical precipitation, adsorption, and reverse osmosis, can reduce the concentration of uranium to some extent, but these methods have low treatment efficiency, high cost, complex operation, and may cause secondary pollution, making it difficult to meet the challenges of large-scale and persistent pollution. Therefore, it is urgent to develop an efficient, low-cost, and environmentally friendly uranium removal technology to meet the increasingly severe water pollution control needs.

[0003] In recent years, electrochemical removal technology has gradually become an effective means to solve water pollution problems due to its fast reaction speed, simple operation, and low energy consumption. The choice of electrode material directly affects the efficiency of electrochemical removal. Currently, strontium titanate electrodes have been widely used in water treatment due to their good chemical stability and electrochemical performance. However, the cyclic stability of strontium titanate electrodes is poor, and they are prone to activity decay during use, resulting in short service life and the need for frequent replacement, which increases operational costs and maintenance difficulties. Although some studies have attempted to enhance the performance of strontium titanate electrodes by doping transition metals, the type of doped transition metal, the doping ratio, and the reaction conditions during the doping process can all cause changes in the active sites and structure of the strontium titanate electrode surface, thereby affecting the adsorption efficiency and stability of uranium.

[0004] Therefore, it is of great scientific value and has wide practical application prospects to develop an efficient and stable electrode suitable for the treatment of low-concentration uranium-polluted water bodies. SUMMARY

[0005] The purpose of the present application is to provide a nickel strontium titanate electrode for removing uranium and a preparation method and application thereof, to solve the problems of low removal efficiency, poor stability, and short service life of existing electrode materials in the process of removing uranium.

[0006] To achieve the above-mentioned purpose, the present application provides a preparation method of a nickel strontium titanate electrode for removing uranium, comprising the following preparation steps:

[0007] S1, mixing a titanium source, an alcohol amine carrier, and an alkaline solution to obtain a precursor solution;

[0008] S2, adding a nickel source and a strontium source to the precursor solution, ultrasonicating, and hydrothermally reacting to obtain a nickel strontium titanate material;

[0009] S3, coating the nickel strontium titanate material on a surface of a carbon fiber base material to obtain a nickel strontium titanate electrode from which uranium is removed.

[0010] In the present application, the specific process of S1 includes adding a titanium source to an alcohol amine carrier, and after stirring at a temperature of 60-70°C for 2-3h, adding a basic solution for mixing.

[0011] In the present application, the titanium source in S1 includes at least one of tetrabutyl titanate, acid tetraisopropyl titanate, and n-octyl titanate, the alcohol amine carrier includes at least one of ethanol amine, monoethanol amine, and propanol amine, the basic solution includes at least one of a sodium hydroxide solution, a potassium hydroxide solution, and ammonia water, and the concentration of the basic solution is 2-2.5 mol / L.

[0012] In the present application, the alcohol amine carrier is selected to provide a stable environment for introducing the nickel element during the reaction.

[0013] In the present application, the volume ratio of the titanium source, the alcohol amine carrier, and the basic solution in S1 is 2-4:20-30:40-60.

[0014] In the present application, the temperature for mixing in S1 is 60-70°C, and the mixing time is 1-1.5h.

[0015] In the present application, the nickel source in S2 is a nickel-containing salt solution with a concentration of 0.05-0.1 mol / L, and the strontium source is a strontium-containing salt solution with a concentration of 0.3-0.5 mol / L; the volume ratio of the nickel source, the strontium source, and the basic solution is 2-3:5-7:40-60.

[0016] In the present application, the nickel-containing salt solution includes at least one of a nickel chloride solution, a nickel nitrate solution, and a nickel sulfate solution, and the strontium-containing salt solution includes at least one of a strontium nitrate solution, a strontium chloride solution, and a strontium acetate solution.

[0017] In the present application, the ultrasonicating time in S2 is 4-6h.

[0018] In the present application, the hydrothermal reaction temperature in S2 is 170-190°C, and the hydrothermal reaction time is 20-30h.

[0019] In the present application, after the hydrothermal reaction in S2 is completed, a hydrothermal reaction product is obtained, the hydrothermal reaction product is sequentially washed with hydrochloric acid and water, and then placed in a centrifuge for centrifugation at a centrifugal speed of 700-800 rpm for 30-50 min to obtain a centrifugal slurry, which is placed in a drying box for drying at a temperature of 70-90°C for 10-12h to obtain the nickel strontium titanate material.

[0020] In the present application, the carbon fiber base material in S3 includes at least one of carbon cloth electrode, carbon felt electrode, carbon paper electrode, and the thickness of the strontium nickel titanate material coating is 0.3-0.5mm.

[0021] The present application also provides a uranium-removed strontium nickel titanate electrode prepared by the preparation method of the uranium-removed strontium nickel titanate electrode.

[0022] The present application also provides the application of the uranium-removed strontium nickel titanate electrode in removing uranium in wastewater.

[0023] The present application has the following beneficial effects:

[0024] The present application provides a preparation method of a uranium-removed strontium nickel titanate electrode, which comprises the following preparation steps: S1, mixing a titanium source, an alcohol amine carrier and an alkaline solution to obtain a precursor solution; S2, adding a nickel source and a strontium source to the precursor solution, ultrasonicating and hydrothermally reacting to obtain a strontium nickel titanate material; and S3, coating the strontium nickel titanate material on the surface of a carbon fiber base material to obtain a uranium-removed strontium nickel titanate electrode.

[0025] In the present application, a large number of active sites are formed on the surface of the strontium titanate electrode by doping nickel metal, the electronic structure of nickel ions has a strong interaction with uranium ions, and uranium ions can be specifically captured through complexation reaction, electrostatic adsorption and other modes, thereby improving the selective adsorption capacity for uranium.

[0026] The nickel doping not only increases the number of active sites, but also optimizes the electronic transmission characteristics of the electrode: the high stability of strontium titanate provides structural support for the electrode, and the high electrochemical activity of nickel accelerates electron transfer, so that the electrode response current reaches-3.95~-3.8mA. The high response current promotes the electrochemical reduction reaction of uranium ions on the electrode surface, and significantly improves the removal efficiency.

[0027] In the present application, nickel metal doping is selected, nickel has certain acid and alkali resistance, is not easy to be protonated and corroded under acidic conditions, and will not form hydroxide precipitate under alkaline conditions. Strontium titanate has extremely strong chemical inertness and structural stability, the crystal structure is dense, and the chemical bond energy is high, and is not easy to hydrolyze or lattice collapse under acidic or alkaline conditions. Therefore, the uranium-removed strontium nickel titanate electrode prepared always maintains the adsorption and electrochemical reduction activity for uranium ions in a pH3-9 environment.

[0028] In the present application, through the synergistic effect of nickel doping and carbon fiber base material, the charge transfer resistance of the electrode is significantly reduced, ensuring that the steps of adsorption, electron transfer and electrochemical reduction of uranium ions are carried out efficiently and continuously, avoiding the problem of slow reaction kinetics caused by blocked electron transfer, and making the uranium removal efficiency stable at 97%-99% within 6h.

[0029] The present application forms a porous and uniformly dispersed composite structure of the prepared uranium-removing nickel strontium titanate electrode through the combined process of nickel doping, hydrothermal reaction and carbon cloth coating; wherein the nickel doping introduces abundant metal active sites and optimizes the electrochemical performance, the hydrothermal reaction promotes the full formation of mesoporous / microporous structure, and the carbon cloth coating reduces the charge transfer resistance and stabilizes the active layer loading, the three synergistically expand the electrode electrochemical active area, shorten the uranium ion mass transfer distance, accelerate the combination of uranium ions and active sites and the electrochemical reaction process, and greatly improve the uranium selectivity and removal efficiency.

[0030] The preparation method provided by the present application selects low-cost raw materials, and has a simple preparation process and easy operation, and is suitable for large-scale production.

[0031] The present application further limits the temperature of the hydrothermal reaction in S2 to 170-190 DEG C, and the time of the hydrothermal reaction to 20-30h, by controlling the hydrothermal reaction conditions, the structure characteristics of the nickel strontium titanate are improved, a composite structure with high electrochemical activity and abundant metal ion sites is formed, ensuring that the nickel ions are uniformly dispersed in the strontium titanate lattice, avoiding the waste of active sites or uneven electrochemical performance caused by local aggregation.

[0032] The uranium-removing nickel strontium titanate electrode prepared by the preparation method of the present application can efficiently remove uranium elements in wastewater, and the removal efficiency reaches more than 97% within 6h of treatment time. After 7 cycles, the removal efficiency still remains at 92%, with excellent stability.

[0033] The uranium-removing nickel strontium titanate electrode prepared by the preparation method of the present application can still maintain a high removal efficiency in the range of pH 3-9, and can be widely applied to various scale water treatment systems, with significant market prospects and wide application potential.

[0034] The technical solutions of the present application are described in further detail below by means of the accompanying drawings and examples. BRIEF DESCRIPTION OF DRAWINGS

[0035] Figure 1 is the response current test result graph of the uranium-removing nickel strontium titanate electrode prepared in Examples 1-3;

[0036] Figure 2 is the response current test result graph of the strontium titanate electrode prepared in Comparative Example 1 and the nickel titanate electrode prepared in Comparative Example 2;

[0037] Figure 3 is the electrochemical active area test result graph of the uranium-removing nickel strontium titanate electrode prepared in Examples 1-3;

[0038] Figure 4is a graph of the electrochemically active area test results of the strontium titanate electrode prepared in Comparative Example 1 and the nickel titanate electrode prepared in Comparative Example 2;

[0039] Figure 5 is a graph of the uranium removal efficiency test results of the uranium-removing nickel strontium titanate electrode prepared in Examples 1-3;

[0040] Figure 6 is a graph of the uranium removal efficiency test results of the strontium titanate electrode prepared in Comparative Example 1 and the nickel titanate electrode prepared in Comparative Example 2;

[0041] Figure 7 is a graph of the uranium removal efficiency test results of the uranium-removing nickel strontium titanate electrode prepared in Example 3 under different pH conditions;

[0042] Figure 8 is a graph of the uranium removal efficiency test results of the uranium-removing nickel strontium titanate electrode prepared in Example 3 after being cycled 7 times under the same conditions. DETAILED DESCRIPTION

[0043] The present application will be further described below in conjunction with the accompanying drawings and examples. Unless otherwise defined, the technical terms or scientific terms used in the present application shall be understood as having the usual meaning understood by a person having ordinary skill in the art to which the present application pertains. The features mentioned above or the features mentioned in the specific examples can be combined in any manner, and these specific examples are only used to illustrate the present application and are not used to limit the scope of the present application.

[0044] Example 1

[0045] A method for preparing a uranium-removing nickel strontium titanate electrode, comprising the following preparation steps:

[0046] S1, 3 mL of tetrabutyl titanate was added to a beaker containing 30 mL of ethanolamine, stirred at a temperature of 60°C for 3 h, then 40 mL of a sodium hydroxide solution with a concentration of 2.2 mol / L was added, the temperature was kept unchanged, and mixed for 1.5 h to obtain a precursor solution;

[0047] S2, 2.5 mL of a nickel chloride solution with a concentration of 0.1 mol / L and 6 mL of a strontium nitrate solution with a concentration of 0.5 mol / L were added to the above-mentioned precursor solution, and ultrasonic treatment was performed for 5 h to obtain a mixed solution, and then the mixed solution was placed in a polytetrafluoroethylene reaction kettle, and hydrothermal reaction was performed at a temperature of 170°C for 30 h to obtain a hydrothermal reaction product, which was sequentially washed with hydrochloric acid and water, and then placed in a centrifuge, and centrifuged at a centrifugal speed of 700 rpm for 50 min to obtain a centrifugal slurry, which was placed in a drying box and dried at a temperature of 90°C for 10 h to obtain a nickel strontium titanate material;

[0048] S3, the nickel strontium titanate material is coated on the surface of the carbon cloth electrode, the coating thickness is 0.3mm, a nickel strontium titanate electrode for removing uranium is obtained, and is recorded as NiSrTiO3-1.

[0049] Example 2

[0050] A preparation method of a nickel strontium titanate electrode for removing uranium comprises the following preparation steps:

[0051] S1, 4mL of tetrabutyl titanate is added to a beaker containing 25mL of ethanolamine, stirring is carried out at a temperature of 70℃ for 2.5h, then 60mL of a sodium hydroxide solution with a concentration of 2mol / L is added, the temperature is kept unchanged, and mixing is carried out for 1h, so that a precursor solution is obtained;

[0052] S2, 2mL of a nickel chloride solution with a concentration of 0.05mol / L and 5mL of a strontium nitrate solution with a concentration of 0.4mol / L are added to the precursor solution, ultrasonic treatment is carried out for 4h, so that a mixed solution is obtained, then the mixed solution is placed in a polytetrafluoroethylene reaction kettle, hydrothermal reaction is carried out at a temperature of 180℃ for 20h, so that a hydrothermal reaction product is obtained, the hydrothermal reaction product is sequentially washed with hydrochloric acid and water, then is placed in a centrifugal machine, centrifugation is carried out at a centrifugal speed of 750rpm for 30min, so that a centrifugal slurry is obtained, the centrifugal slurry is placed in a drying box, drying is carried out at a temperature of 80℃ for 12h, so that a nickel strontium titanate material is obtained;

[0053] S3, the nickel strontium titanate material is coated on the surface of the carbon cloth electrode, the coating thickness is 0.4mm, a nickel strontium titanate electrode for removing uranium is obtained, and is recorded as NiSrTiO3-2.

[0054] Example 3

[0055] A preparation method of a nickel strontium titanate electrode for removing uranium comprises the following preparation steps:

[0056] S1, 2mL of tetrabutyl titanate is added to a beaker containing 20mL of ethanolamine, stirring is carried out at a temperature of 65℃ for 2h, then 50mL of a sodium hydroxide solution with a concentration of 2.5mol / L is added, the temperature is kept unchanged, and mixing is carried out for 1.2h, so that a precursor solution is obtained;

[0057] S2, 3mL of a nickel chloride solution with a concentration of 0.075mol / L and 7mL of a strontium nitrate solution with a concentration of 0.3mol / L are added to the precursor solution, ultrasonic treatment is carried out for 6h, so that a mixed solution is obtained, then the mixed solution is placed in a polytetrafluoroethylene reaction kettle, hydrothermal reaction is carried out at a temperature of 190℃ for 25h, so that a hydrothermal reaction product is obtained, the hydrothermal reaction product is sequentially washed with hydrochloric acid and water, then is placed in a centrifugal machine, centrifugation is carried out at a centrifugal speed of 800rpm for 40min, so that a centrifugal slurry is obtained, the centrifugal slurry is placed in a drying box, drying is carried out at a temperature of 70℃ for 11h, so that a nickel strontium titanate material is obtained;

[0058] S3, coating the strontium titanate material on the surface of the carbon cloth electrode with a coating thickness of 0.5 mm to obtain a strontium titanate electrode from which uranium is removed, denoted as SrTiO3.

[0059] Comparative Example 1

[0060] A preparation method of a strontium titanate electrode includes the following preparation steps:

[0061] S1, adding 2 mL of tetrabutyl titanate into a beaker containing 20 mL of ethanolamine, stirring at a temperature of 65°C for 2 h, then adding 50 mL of a sodium hydroxide solution with a concentration of 2.5 mol / L, keeping the temperature unchanged, and mixing for 1.2 h to obtain a precursor solution;

[0062] S2, adding 7 mL of a strontium nitrate solution with a concentration of 0.3 mol / L to the precursor solution, ultrasonicating for 6 h to obtain a mixed solution, then placing the mixed solution in a polytetrafluoroethylene reaction kettle, and performing hydrothermal reaction at a temperature of 190°C for 25 h to obtain a hydrothermal reaction product, then sequentially washing the hydrothermal reaction product with hydrochloric acid and water, placing the hydrothermal reaction product in a centrifuge, centrifuging at a centrifugal speed of 800 rpm for 40 min to obtain a centrifuged slurry, and placing the centrifuged slurry in a drying box, drying at a temperature of 70°C for 11 h to obtain a strontium titanate material;

[0063] S3, coating the strontium titanate material on the surface of the carbon cloth electrode with a coating thickness of 0.5 mm to obtain a strontium titanate electrode from which uranium is removed, denoted as SrTiO3.

[0064] Comparative Example 2

[0065] A preparation method of a nickel titanate electrode includes the following preparation steps:

[0066] S1, adding 2 mL of tetrabutyl titanate into a beaker containing 20 mL of ethanolamine, stirring at a temperature of 65°C for 2 h, then adding 50 mL of a sodium hydroxide solution with a concentration of 2.5 mol / L, keeping the temperature unchanged, and mixing for 1.2 h to obtain a precursor solution;

[0067] S2, adding 3 mL of a nickel chloride solution with a concentration of 0.75 mol / L to the precursor solution, ultrasonicating for 6 h to obtain a mixed solution, then placing the mixed solution in a polytetrafluoroethylene reaction kettle, and performing hydrothermal reaction at a temperature of 190°C for 25 h to obtain a hydrothermal reaction product, then sequentially washing the hydrothermal reaction product with hydrochloric acid and water, placing the hydrothermal reaction product in a centrifuge, centrifuging at a centrifugal speed of 800 rpm for 40 min to obtain a centrifuged slurry, and placing the centrifuged slurry in a drying box, drying at a temperature of 70°C for 11 h to obtain a nickel titanate material;

[0068] S3, coating the nickel titanate material on the surface of the carbon cloth electrode, the coating thickness is 0.5 mm, to obtain a uranium-removed nickel titanate electrode, recorded as NiTiO3.

[0069] Performance test:

[0070] The response current of the uranium-removed nickel strontium titanate electrode prepared in Examples 1-3 was tested by an electrochemical workstation, and the results are shown in Figure 1 From Figure 1 it can be seen that the response current of NiSrTiO3-1 prepared in Example 1 is -3.85 mA, the response current of NiSrTiO3-2 prepared in Example 2 is -3.81 mA, and the response current of NiSrTiO3-3 prepared in Example 3 is -3.95 mA.

[0071] The response current of the strontium titanate electrode prepared in Comparative Example 1 and the nickel titanate electrode prepared in Comparative Example 2 was tested by an electrochemical workstation, and the results are shown in Figure 2 From Figure 2 it can be seen that the response current of SrTiO3 prepared in Comparative Example 1 is -1.32 mA, and the response current of NiTiO3 prepared in Comparative Example 2 is -1.05 mA.

[0072] The electrochemical active area of the uranium-removed nickel strontium titanate electrode prepared in Examples 1-3 was tested by an electrochemical workstation, and the results are shown in Figure 3 From Figure 3 it can be seen that the electrochemical active area of NiSrTiO3-1 prepared in Example 1 is 109 cm 2 , the electrochemical active area of NiSrTiO3-2 prepared in Example 2 is 114 cm 2 , and the electrochemical active area of NiSrTiO3-3 prepared in Example 3 is 122 cm 2 .

[0073] The electrochemical active area of the strontium titanate electrode prepared in Comparative Example 1 and the nickel titanate electrode prepared in Comparative Example 2 was tested by an electrochemical workstation, and the results are shown in Figure 4 From Figure 4 it can be seen that the electrochemical active area of SrTiO3 prepared in Comparative Example 1 is 46 cm 2 , and the electrochemical active area of NiTiO3 prepared in Comparative Example 2 is 34 cm 2 .

[0074] Using the uranium-removed strontium nickel titanate electrode prepared in Examples 1-3 as the anode and a titanium sheet as the cathode, respectively, they were placed in 200 mL of a mixed solution containing coexisting ions (the mixed solution included: uranium ions, chloride ions, nitrate ions, bicarbonate ions, sodium ions, potassium ions, and magnesium ions, with each ion concentration of 10 mg / L and the pH of the mixed solution being 5). A current density of 5 mA / cm² was applied. 2 The uranium removal effect was tested at an experimental temperature of 25℃, and the results are as follows: Figure 5 As shown.

[0075] from Figure 5 It can be seen that the NiSrTiO3-1 prepared in Example 1 achieved a uranium removal efficiency of 98.2% within 6 hours, the NiSrTiO3-2 prepared in Example 2 achieved a uranium removal efficiency of 99.1% within 6 hours, and the NiSrTiO3-3 prepared in Example 3 achieved a uranium removal efficiency of 99.8% within 6 hours. This confirms that the strontium nickel titanate electrode for uranium removal prepared in this invention has excellent selectivity and high removal efficiency for uranium.

[0076] Using the strontium titanate electrode prepared in Comparative Example 1 and the nickel titanate electrode prepared in Comparative Example 2 as anodes and a titanium sheet as cathode, respectively, they were placed in 200 mL of a mixed solution containing coexisting ions (the mixed solution included: uranium ions, chloride ions, nitrate ions, bicarbonate ions, sodium ions, potassium ions, and magnesium ions, with each ion concentration of 10 mg / L and the pH of the mixed solution being 5). A current density of 5 mA / cm² was applied. 2 The uranium removal effect was tested at an experimental temperature of 25℃, and the results are as follows: Figure 6 As shown.

[0077] from Figure 6 It can be seen that the SrTiO3 prepared in Comparative Example 1 had a uranium removal rate of 60.5% within 6 hours, and the NiTiO3 prepared in Comparative Example 2 had a uranium removal rate of 37.6% within 6 hours. Both are significantly lower than the removal efficiency of the uranium removal electrode of strontium nickel titanate prepared by the method of the present invention.

[0078] Using the uranium-removed strontium nickel titanate electrode prepared in Example 3 as the anode and a titanium sheet as the cathode, the electrodes were placed in 200 mL mixed solutions containing coexisting ions at different pH values ​​(pH 3, 4, 5, 6, 7, 8, and 9). The mixed solutions included uranium ions, chloride ions, nitrate ions, bicarbonate ions, sodium ions, potassium ions, and magnesium ions, with each ion concentration of 10 mg / L and a pH of 5. A current density of 5 mA / cm² was applied. 2 The uranium removal effect was tested at an experimental temperature of 25℃, and the results are as follows: Figure 7 As shown. From Figure 7It can be seen that the removal rate of uranium by the NiSrTiO3-3 prepared in Example 3 is 96.5%-99.8% in the pH range of 3-9, which proves that the nickel-strontium titanate electrode prepared by the present application for removing uranium has a wide pH range of use.

[0079] The nickel-strontium titanate electrode prepared in Example 3 for removing uranium was used as an anode, and a titanium sheet was used as a cathode, and then they were placed in a 200 mL mixed solution containing coexisting ions (the mixed solution included uranium ions, chloride ions, nitrate ions, bicarbonate ions, sodium ions, potassium ions, and magnesium ions, and the concentration of each ion was 10 mg / L, and the pH of the mixed solution was 5). The removal of uranium was carried out at a current density of 5 mA / cm 2 2 for 6 h, and then the mixed solution was replaced (the ion concentration and pH of the mixed solution were not changed), and the removal efficiency of uranium was recorded after 7 cycles. The results are shown in Table 1. Figure 8 It can be seen that the removal efficiency of uranium remained at 98.1% after 8 cycles, which proves that the nickel-strontium titanate electrode prepared by the method of the present application for removing uranium has excellent electrochemical stability and service life. Figure 8

[0080] Finally, it should be pointed out that the above examples are only used to illustrate the technical solutions of the present application but not to limit them. Although the present application has been described in detail with reference to the preferred embodiments, it should be understood by those skilled in the art that the technical solutions of the present application can still be modified or replaced by equivalents, and these modifications or replacements cannot make the modified technical solutions deviate from the spirit and scope of the technical solutions of the present application.​

Claims

1. A method for preparing a nickel strontium titanate electrode from which uranium is removed, characterized in that, The preparation steps include the following: S1. Mix the titanium source, the alkanolamine carrier, and the alkaline solution to obtain the precursor solution; S2. Add nickel source and strontium source to the above precursor solution, sonicate, and perform hydrothermal reaction to obtain strontium nickel titanate material; S3. Strontium nickel titanate material is coated on the surface of carbon fiber substrate material to obtain uranium-removing strontium nickel titanate electrode; The titanium source in S1 includes at least one of tetrabutyl titanate, tetraisopropyl titanate, and n-octyl titanate; the amine carrier includes at least one of ethanolamine, monoethanolamine, and propanolamine; and the alkaline solution includes at least one of sodium hydroxide solution, potassium hydroxide solution, and ammonia water, with a concentration of 2-2.5 mol / L. In S2, the nickel source is a nickel-containing salt solution with a concentration of 0.05-0.1 mol / L, and the strontium source is a strontium-containing salt solution with a concentration of 0.3-0.5 mol / L; the volume ratio of the nickel source, strontium source, and alkaline solution is 2-3:5-7:40-60. The hydrothermal reaction temperature in S2 is 170-190℃, and the hydrothermal reaction time is 20-30h; The carbon fiber substrate material in S3 includes at least one of carbon cloth electrode, carbon felt electrode, and carbon paper electrode, and the thickness of the strontium nickel titanate coating is 0.3-0.5 mm.

2. The method of claim 1, wherein the method is characterized by: The volume ratio of titanium source, amine carrier, and alkaline solution in S1 is 2-4:20-30:40-60.

3. The method of claim 1, wherein the method further comprises the step of: The mixing temperature in S1 is 60-70℃, and the mixing time is 1-1.5h. ​ 4. The method of claim 1, wherein the method further comprises the step of: 5 annealing the nickel strontium titanate electrode at a temperature of about 600 °C to about 800 °C for about 1 hour to about 10 hours in air. Nickel-containing salt solutions include at least one of nickel chloride solution, nickel nitrate solution, and nickel sulfate solution, and strontium-containing salt solutions include at least one of strontium nitrate solution, strontium chloride solution, and strontium acetate solution.

5. A strontium nickel titanate electrode for uranium removal prepared by the method for preparing a strontium nickel titanate electrode for uranium removal according to any one of claims 1-4.

6. The application of the strontium nickel titanate electrode for uranium removal as an anode in wastewater as described in claim 5.

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