Radiation resistant separation material for thorium-barium separation and method of making the same

Abstract

The application belongs to the technical field of medical radioisotopes, and particularly relates to a radiation-resistant separation material for thorium-barium separation and a preparation method thereof. The preparation method comprises the following steps: preparing an active material, preparing a polyacrylonitrile matrix, preparing a composite material precursor solution, and forming a composite material. The prepared separation material has good thorium-barium separation performance and can resist 300 kGy absorbed dose of radiation, and can be used for radiation-resistant 228 Th- 224 Ra generator preparation.

Description

Technical Field

[0001] This invention belongs to the field of medical radioisotope technology, specifically relating to a radiation-resistant separation material for thorium-barium separation and its preparation method. Background Technology

[0002] Targeted alpha radionuclide therapy (TAT) involves binding an alpha nuclide to a carrier, utilizing the carrier's selectivity to deliver the alpha nuclide to tumor cells and release alpha particles to disrupt their structure, thereby targeting and treating the cancerous lesions. Because the linear energy transfer density (LET) of alpha particles is two to three orders of magnitude higher than that of beta particles (100 keV / μm vs 0.2 keV / μm), most of the total energy can be deposited within the tumor cells, causing DNA double-strand breaks and preventing repair, thus improving therapeutic efficacy. Furthermore, alpha particles have a shorter range in human tissue (50-100 μm, approximately 5-10 cell diameters), effectively killing tumor cells with high cytotoxicity while causing very limited damage to surrounding healthy tissues. Therefore, alpha-particle-based radiopharmaceuticals offer better therapeutic efficacy and fewer side effects than common beta-particle radiopharmaceuticals. 224 Ra is a typical alpha medical nuclide with a half-life of 3.66 days and a maximum alpha energy of 5.69 MeV. Utilizing Ra's bone-affinity properties... 224 Ra has been used to treat ankylosing spondylitis, and there is now a great deal of research on its application in liposomes, nanoparticle encapsulation, and calcium-carbon microspheres. 224 Research on Ra treatment drugs. Furthermore, it is possible to utilize [the drug] concurrently with cancer treatment. 224 Ra at 241.0 keV (4.10%) abundant gamma rays, combined with single-photon emission computed tomography (SPECT) technology for real-time monitoring of treatment efficacy. Therefore, 224 Ra is an alpha medical nuclide with broad application prospects. 224 Ra is mainly prepared by obtaining its parent nuclide. 228 It was obtained from Th, but because 228 Th and 224Ra and its series of daughter nuclides emit a large number of alpha particles. Traditional separation materials, such as anion and cation exchange resins and extraction resins, exhibit significantly reduced performance after contact with aqueous solutions and irradiation. Patent application (202411261811.7) discloses a method for extracting lead-212 and bismuth-212 from the decay chain of thorium-232 using anion exchange resin columns. Patent application (202311390371.0) discloses a method for separating actinium from an irradiated thorium target using cation exchange resins, UTEVA or TK200 resin, DGA resin, and LN resin. Patent application (202211149724.3) discloses a purification process for separating actinium-225 from thorium, actinium, and radium using LN resin and P204 resin. Patent application (202410556038.0) discloses a method for efficiently separating thorium and radium using anion exchange resins. The aforementioned patented methods all employ materials such as anion and cation exchange resins and extraction resins to separate thorium from its daughter nuclides, without addressing the radiation resistance of the separation materials themselves. Summary of the Invention

[0003] The purpose of this invention is to solve the above-mentioned problems and provide a new method for preparing separation materials with good thorium-barium separation performance and radiation resistance, which can be used for radiation-resistant applications. 228 Th- 224 Preparation of Ra generator.

[0004] Therefore, a first aspect of the present invention provides a method for preparing a radiation-resistant separation material for thorium-barium separation, the method comprising:

[0005] (1) Preparation of active material: Add carbon material to a mixture of acid solution and sodium nitrate, stir and maintain the first temperature; then gradually add strong oxidant while maintaining the second temperature; after the addition is complete, stir the suspension at the third temperature; slowly add water to raise the temperature to the fourth temperature and maintain the temperature; then add water and hydrogen peroxide in sequence; centrifuge and wash the mixture multiple times until the pH of the supernatant is neutral; remove the supernatant and freeze-dry the precipitate to obtain active material powder;

[0006] (2) Preparation of polyacrylonitrile matrix: gradually add polyacrylonitrile powder to the first organic solvent at the fifth temperature, and stir vigorously to completely dissolve the polyacrylonitrile;

[0007] (3) Preparation of composite material precursor solution: The active material powder obtained in step (1) is mixed with the second organic solvent and sonicated. The resulting solution is gradually added to the polyacrylonitrile matrix solution obtained in step (2) to obtain the composite material precursor solution.

[0008] (4) Composite material molding: The composite material precursor solution is dropped into water and solidified to form thorium adsorption material composite balls; the thorium adsorption material composite balls are soaked in water and dried at the sixth temperature; then water is added and the thorium adsorption material composite balls are crushed by a high-speed crusher, and the crushed sample is freeze-dried to obtain radiation-resistant separation material for thorium-barium separation.

[0009] In step (4) above, the inventive principle includes: the organic solvent in the precursor solution of the composite material penetrates the droplets into the water, so that the composite material is formed into a spherical shape in the water bath.

[0010] As a preferred embodiment, the above-described method for preparing radiation-resistant separation materials for thorium-barium separation...

[0011] In step (1), the relative amounts of each component are: 2g of carbon material, 30-80mL of acid solution, 1-2g of sodium nitrate, 6-10g of strong oxidant, and 8-12g of hydrogen peroxide. The above preferred range can ensure that the carbon material is fully oxidized and stripped while avoiding excessive oxidation that could lead to structural damage or excessive loss of functional groups, thereby obtaining an active material with high specific surface area and abundant surface functional groups, which is beneficial for subsequent adsorption of thorium.

[0012] In step (2), the relative amounts of each component are: 10g of polyacrylonitrile powder and 25-35mL of the first organic solvent; within this concentration range, the polyacrylonitrile powder can be fully dissolved to form a uniform, transparent, and viscous solution suitable for subsequent compounding.

[0013] In step (3), the relative amounts of each component are: 300-900 mg of active material powder and 30 mL of the second organic solvent. Within this range, the active material can ensure sufficient adsorption sites without causing agglomeration or uneven dispersion due to excessive amounts.

[0014] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the carbon material is one or more of carbon powder, activated carbon, graphite powder, and carbon fiber.

[0015] As a preferred embodiment, in the above-described method for preparing the radiation-resistant separation material for thorium-barium separation, the acid solution is one or more of hydrochloric acid, nitric acid, sulfuric acid, and phosphoric acid. The aforementioned acid solution possesses strong dehydrating and oxidizing properties.

[0016] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the strong oxidant is one or more selected from potassium permanganate, potassium chlorate, and potassium dichromate. These strong oxidants can better achieve the oxidative stripping of carbon materials. The strong oxidants possess strong oxidizing power and mild, controllable reaction conditions, which facilitates the effective oxidation and stripping of carbon materials.

[0017] As a preferred embodiment, the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation includes a first temperature of 0-5°C, such as under ice bath conditions, to prevent excessive exothermic reaction; a second temperature of 15-25°C to ensure stable reaction; and a third temperature of 30-40°C, during which the suspension is stirred for 5-30 minutes to facilitate uniform mixing and initial reaction of the reactants.

[0018] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the fourth temperature is 60~120℃, and the holding time of the fourth temperature is 15~30 minutes, which promotes the in-depth reaction and further stripping of the material. At the same time, hydrogen peroxide also plays a role in purifying and oxidizing the residues.

[0019] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the fifth temperature is 30~60℃ to ensure that the polyacrylonitrile is completely dissolved, with no particle residue, and to form a uniform and transparent PAN solution.

[0020] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the sixth temperature is 50~80℃, which is used to dry the soaked composite balls or particles to remove moisture, while avoiding high temperature damage to the material structure.

[0021] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the time for vigorous stirring in step (2) is 1 to 2 hours.

[0022] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the ultrasonic time in step (3) is 30-60 minutes.

[0023] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation material for thorium-barium separation, in step (4), the soaking time in water is 1 to 2 hours to remove residual solvent, unreacted monomers or impurities, and to stabilize the material structure.

[0024] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, the first organic solvent and the second organic solvent are each one or more of dimethyl sulfoxide and N,N-dimethylformamide. These solvents possess characteristics of high boiling point, strong polarity, and strong solubility for polyacrylonitrile, while also exhibiting good dispersing effects on active materials, making them crucial for achieving high-quality composite precursor solutions.

[0025] As a preferred embodiment, in the above-mentioned method for preparing radiation-resistant separation materials for thorium-barium separation, step (4) includes freeze-drying: freezing at -10℃ to -90℃ for 5 to 40 hours and vacuum drying for 6 to 30 hours. Freeze-drying can preserve the porous structure and specific surface area of ​​the material to the greatest extent, avoid shrinkage and pore collapse caused by hot air drying, and help improve adsorption performance.

[0026] According to one specific embodiment of the present invention, step (2) involves preparing the polyacrylonitrile matrix: An organic solvent is placed in a flask, and the flask is placed in an oil bath preheated to 30-60°C. Polyacrylonitrile powder is gradually added to the flask, and the mixture is stirred vigorously for approximately 1-2 hours until the polyacrylonitrile is completely dissolved.

[0027] A second aspect of the present invention provides a radiation-resistant separation material for the separation of thorium and barium, said radiation-resistant separation material being prepared by the preparation method described above. The radiation-resistant separation material for the separation of thorium and barium satisfies the following condition: the radiation-resistant separation material has an adsorption capacity for thorium ≥ 7.5 mg·g at pH=3. -1 The adsorption capacity for barium is ≤0.15 mg·g. -1 The radiation-resistant separation material exhibits no structural change under irradiation doses of ≤300 kGy; the adsorption capacity of the radiation-resistant separation material for thorium is ≥7.5 mg·g under irradiation doses of ≤300 kGy. -1 The adsorption capacity for barium is ≤0.15 mg·g. -1 .

[0028] Compared with the prior art, the present invention has the following advantages and beneficial effects:

[0029] 1. This invention can prepare a separation material for thorium-barium separation, with an adsorption capacity for thorium that meets the requirements. 228 Th- 224 The Ra generator has requirements for thorium adsorption, while its adsorption performance for barium (the simulant of radium) is negligible, thus exhibiting good thorium-barium separation performance.

[0030] 2. The separation material prepared by this invention for thorium-barium separation also has good radiation resistance and can be used to prepare radiation-resistant materials. 228 Th- 224 Ra generator.

[0031] The above description is merely an overview of the technical solution of the present invention. In order to better understand the technical means of the present invention and to implement it in accordance with the contents of the specification, and in order to make the above and other objects, features and advantages of the present invention more apparent and understandable, specific embodiments of the present invention are described below. Attached Figure Description

[0032] Figure 1 SEM images of the separated material prepared in Example 1 are shown.

[0033] Figure 2 The adsorption capacity of the radiation-resistant separation material of Example 2 for Th and Ba is shown under different pH conditions.

[0034] Figure 3 The FTIR spectra of the radiation-resistant separation material of Example 3 after irradiation with different absorbed doses are shown.

[0035] Figure 4 The adsorption capacity of the separation material prepared in Example 1 for Th and Ba after irradiation with different absorbed doses of γ is shown. Detailed Implementation

[0036] To make the objectives, technical solutions, and advantages of the embodiments of the present invention clearer, the technical solutions in the embodiments of the present invention are described clearly and completely below. Unless otherwise specified, specific conditions are applied in the embodiments. Reagents or instruments used without a specified manufacturer are all commercially available conventional products.

[0037] The example illustrates a method for preparing a radiation-resistant separation material for thorium-barium separation.

[0038] Example 1:

[0039] 2.0 g of carbon powder was added to a mixture of 30.0 mL concentrated sulfuric acid, 3.0 mL phosphoric acid, and 1.5 g sodium nitrate, while maintaining the temperature at 0°C and stirring continuously. Then, 6.0 g of potassium permanganate was gradually added, while keeping the temperature below 20°C. After the addition was complete, the ice bath was removed, and the suspension was stirred at 35°C for 30 minutes. 60 mL of deionized water was slowly added; the reaction was exothermic, raising the temperature to approximately 95°C and maintaining this temperature for 15 minutes. Then, 280 mL of deionized water and 10 mL of hydrogen peroxide were added sequentially to obtain the reaction mixture. The mixture was centrifuged and washed multiple times until the pH of the supernatant was neutral. The supernatant was removed, and the precipitate was freeze-dried to obtain powder A. 900 mg of powder sample A was added to a 50 mL centrifuge tube, followed by 30 mL of dimethyl sulfoxide. The centrifuge tube was tightly capped and sonicated in an ultrasonic disperser for 30 minutes to obtain solution B. Take 30 ml of N,N-dimethylformamide into a 250 mL flask and place the flask in an oil bath preheated to 60°C. Gradually add 10 g of polyacrylonitrile powder to the flask and stir vigorously for about 2 hours until the polyacrylonitrile is completely dissolved, obtaining solution C. Gradually add solution B to solution C to obtain a mixed solution. Then, using a syringe, add the mixed solution dropwise to deionized water, allowing it to solidify and form a composite spherical material. After soaking in deionized water for about 1 hour, place the composite spherical material in an oven and dry it at 50°C. Then, crush it with water using a high-speed crusher, and freeze-dry the crushed sample to obtain a radiation-resistant separation material that can be used for thorium-barium separation.

[0040] Figure 1 SEM images of the separated material prepared in Example 1 are shown.

[0041] Figure 4 The adsorption capacity of the separation material prepared in Example 1 for Th and Ba after irradiation with different absorbed doses of γ is shown. Figure 4 The equilibrium adsorption capacities (qi) of the separation material for Th(IV) and Ba(II) after irradiation at 0 kGy, 20 kGy, 50 kGy, 100 kGy, 200 kGy, and 300 kGy are shown. e ).like Figure 4 As shown, the adsorption capacity of the separation material for Th varies little with the absorbed irradiation dose, ranging from 7.69 to 8.02 mg·g⁻¹. -1 Between [a certain value] and [a certain value]. At different absorbance doses, the separation material did not show significant adsorption performance for Ba, and its calculated adsorption capacity was all below 0.2 mg·g. -1 The adsorption experiments showed that irradiation did not significantly affect the adsorption capacity of the separation material, indicating that the separation material possesses a certain degree of irradiation stability.

[0042] Example 2:

[0043] 2.0 g of carbon powder was added to a mixture of 50.0 mL concentrated sulfuric acid, 10.0 mL phosphoric acid, and 1.0 g sodium nitrate, while maintaining the temperature at 0°C and stirring continuously. Then, 10.0 g of potassium perchlorate was gradually added, while keeping the temperature below 20°C. After the addition was complete, the ice bath was removed, and the suspension was stirred at 35°C for 30 minutes. 60 mL of deionized water was slowly added; the reaction was exothermic, and the temperature was raised to approximately 95°C and maintained at this temperature for 30 minutes. Then, 280 mL of deionized water and 10 mL of hydrogen peroxide were added sequentially to obtain the reaction mixture. The mixture was centrifuged and washed multiple times until the pH of the supernatant was neutral. The supernatant was removed, and the precipitate was freeze-dried to obtain powder A. 300 mg of powder sample A was added to a 50 mL centrifuge tube, followed by 30 mL of dimethyl sulfoxide. The centrifuge tube was tightly capped and sonicated in an ultrasonic disperser for 30 minutes to obtain solution B. 30 mL of N,N-dimethylformamide was placed in a 250 mL flask and then placed in an oil bath preheated to 60 °C. 10 g of polyacrylonitrile powder was gradually added to the flask, and the mixture was stirred vigorously for approximately 2 hours until the polyacrylonitrile was completely dissolved, yielding solution C. Solution B was gradually added to solution C to obtain a mixed solution. The mixed solution was then added dropwise to deionized water using a syringe, allowing it to solidify and form a composite spherical material. After soaking in deionized water for approximately 1 hour, the composite spherical material was placed in an oven and dried at 60 °C. It was then crushed with water using a high-speed crusher, and the crushed sample was freeze-dried to obtain a radiation-resistant separation material suitable for thorium-barium separation.

[0044] Figure 2 The adsorption capacity of the radiation-resistant separation material of Example 2 for Th and Ba is shown under different pH conditions.

[0045] Adsorption capacity test method: Prepare a mixed solution of Th and Ba (50 ppm each), adjust the pH of the solution to the preset value, add 30 mg of the separation material prepared in this example, and perform adsorption by shaking. Measure the concentrations of Th and Ba ions in the solution before and after adsorption using ICP-OES, and calculate the adsorption capacity of the separation material for Th and Ba according to the following formula. q e :

[0046]

[0047] In the formula, q e The adsorption capacity at adsorption equilibrium (mg·g) -1 ); C 0 and C eRepresent the initial and equilibrium concentrations (mg·L) of (Th or Ba) ions, respectively. -1 ); V It is the volume of the solution (L); m It is the mass (g) of the separated material.

[0048] Adsorption capacity test results explanation: From Figure 2 It can be seen that the adsorption capacity of the separation material prepared in this embodiment for Th increases with increasing pH value, and its adsorption capacity reaches 8.08 mg·g at pH value 3. -1 Meanwhile, the adsorption capacity for Ba is almost negligible under various pH conditions. These results indicate that the prepared separation material can effectively separate barium thorium and exhibits excellent barium thorium separation performance.

[0049] Example 3:

[0050] Add 2.0 g of carbon powder to a mixture of 70.0 mL concentrated sulfuric acid, 10.0 mL phosphoric acid, and 2.0 g sodium nitrate, while maintaining the temperature at 0°C and stirring continuously. Then gradually add 10.0 g of potassium dichromate, while keeping the temperature below 20°C. After the addition is complete, remove the ice bath and stir the suspension at 35°C for 60 minutes. Slowly add 90 mL of deionized water; the reaction is exothermic, raising the temperature to approximately 95°C and maintaining this temperature for 15 minutes. Then add 280 mL of deionized water and 10 mL of hydrogen peroxide sequentially to obtain the reaction mixture. Centrifuge and wash the mixture multiple times until the pH of the supernatant is neutral. Discard the supernatant and freeze-dry the precipitate to obtain powder A. Take 600 mg of powder sample A and add it to a 50 mL centrifuge tube, then add 30 mL of dimethyl sulfoxide, tighten the centrifuge tube cap, and sonicate it in an ultrasonic disperser for 30 min to obtain solution B. 30 mL of N,N-dimethylformamide was placed in a 250 mL flask and then placed in an oil bath preheated to 60 °C. 10 g of polyacrylonitrile powder was gradually added to the flask, and the mixture was stirred vigorously for approximately 2 hours until the polyacrylonitrile was completely dissolved, yielding solution C. Solution B was gradually added to solution C to obtain a mixed solution. The mixed solution was then added dropwise to deionized water using a syringe, allowing it to solidify and form a composite spherical material. After soaking in deionized water for approximately 1 hour, the composite spherical material was placed in an oven and dried at 80 °C. It was then crushed with water using a high-speed crusher, and the crushed sample was freeze-dried to obtain a radiation-resistant separation material suitable for thorium-barium separation.

[0051] Figure 3 The FTIR spectra of the radiation-resistant separation material of Example 3 after irradiation with different absorbed doses are shown.

[0052] Infrared characterization after irradiation: Irradiation time ranged from 0 to 13 days, and the received irradiation dose ranged from 0 to 300 kGy. As can be seen from the figures, the infrared spectra before and after different irradiation doses did not change significantly, indicating that irradiation did not alter the structure of the separation material, demonstrating that the separation material has good radiation resistance.

[0053] This invention utilizes barium as a simulant for radium to test separation performance and radiation resistance. Experimental results confirm that the separation material exhibits good thorium-barium separation performance and excellent radiation resistance, making it suitable for preparing radiation-resistant materials. 228 Th- 224 Ra generator.

[0054] The above are merely preferred embodiments of the present invention and are not intended to limit the present invention. Various modifications and variations can be made to the present invention by those skilled in the art. Any modifications, equivalent substitutions, improvements, etc., made within the spirit and principles of the present invention should be included within the scope of protection of the present invention.

Claims

1. A method for preparing a radiation-resistant separation material for thorium-barium separation, characterized in that, The preparation method includes: (1) Preparation of active material: Add carbon material to a mixture of acid solution and sodium nitrate, stir and maintain the first temperature; then gradually add strong oxidant while maintaining the second temperature; after the addition is complete, stir the suspension at the third temperature; slowly add water to raise the temperature to the fourth temperature and maintain the temperature; then add water and hydrogen peroxide in sequence; centrifuge and wash the mixture multiple times until the pH of the supernatant is neutral; remove the supernatant and freeze-dry the precipitate to obtain active material powder; (2) Preparation of polyacrylonitrile matrix: gradually add polyacrylonitrile powder to the first organic solvent at the fifth temperature, and stir vigorously to completely dissolve the polyacrylonitrile; (3) Preparation of composite material precursor solution: The active material powder obtained in step (1) is mixed with the second organic solvent and sonicated. The resulting solution is gradually added to the polyacrylonitrile matrix solution obtained in step (2) to obtain the composite material precursor solution. (4) Composite material molding: The composite material precursor solution is dropped into water and solidified to form thorium adsorption material composite balls; the thorium adsorption material composite balls are soaked in water and dried at the sixth temperature; then water is added and the thorium adsorption material composite balls are crushed by a high-speed crusher, and the crushed sample is freeze-dried to obtain radiation-resistant separation material for thorium-barium separation.

2. The method for preparing the radiation-resistant separation material for thorium-barium separation according to claim 1, characterized in that, In step (1), the relative amounts of each component are: 2g of carbon material, 30-80mL of acid solution, 1-2g of sodium nitrate, 6-10g of strong oxidant, and 8-12g of hydrogen peroxide; In step (2), the relative amounts of each component are: 10g of polyacrylonitrile powder and 25-35mL of the first organic solvent; In step (3), the relative amounts of each component are: 300-900 mg of active material powder and 30 mL of the second organic solvent.

3. The method for preparing the radiation-resistant separation material for thorium-barium separation according to claim 1, characterized in that, The carbon material is one or more of carbon powder, activated carbon, graphite powder, and carbon fiber.

4. The method for preparing the radiation-resistant separation material for thorium-barium separation according to claim 1, characterized in that, The acid solution is one or more of hydrochloric acid, nitric acid, sulfuric acid, and phosphoric acid; The strong oxidizing agent is one or more of potassium permanganate, potassium chlorate, and potassium dichromate.

5. The method for preparing the radiation-resistant separation material for thorium-barium separation according to claim 1, characterized in that, The first temperature is 0~5℃; The second temperature is 15~25℃; The third temperature is 30~40℃, and the suspension is stirred at the third temperature for 5~30 minutes; The fourth temperature is 60~120℃, and the holding time of the fourth temperature is 15~30 minutes; The fifth temperature range is 30~60℃; The sixth temperature is 50~80℃.

6. The method for preparing the radiation-resistant separation material for thorium-barium separation according to claim 1, characterized in that, In step (2), vigorous stirring is performed for 1 to 2 hours; In step (3), the ultrasound session lasts for 30 to 60 minutes; In step (4), the soaking time in water is 1 to 2 hours.

7. The method for preparing the radiation-resistant separation material for thorium-barium separation according to claim 1, characterized in that, The first organic solvent and the second organic solvent are each one or more of dimethyl sulfoxide and N,N-dimethylformamide.

8. The method for preparing the radiation-resistant separation material for thorium-barium separation according to claim 1, characterized in that, In step (4), freeze drying includes freezing at a temperature of -10℃ to -90℃ for 5 to 40 hours and vacuum drying for 6 to 30 hours.

9. A radiation-resistant separation material for thorium-barium separation, characterized in that, The radiation-resistant separation material is prepared by the preparation method described in any one of claims 1-8.

10. The application of the radiation-resistant separation material according to claim 9 in thorium-barium separation, characterized in that: The radiation-resistant separation material exhibits an adsorption capacity of ≥7.5 mg·g for thorium in a mixed solution of Th and Ba at pH=3. -1 The adsorption capacity for barium is ≤0.15 mg·g. -1 ; The structure of the radiation-resistant separation material remains unchanged under irradiation doses of ≤300 kGy; The radiation-resistant separation material exhibits an adsorption capacity of ≥7.5 mg·g for thorium at an irradiation dose ≤300 kGy. -1 The adsorption capacity for barium is ≤0.15 mg·g. -1 .

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