Resin-based composite nuclear radiation shielding material containing uranium compound and preparation method of resin-based composite nuclear radiation shielding material

Abstract

The invention provides a preparation method of a resin-based composite nuclear radiation shielding material containing a uranium compound, which comprises the following steps: step 1, weighing dibenzoyl peroxide and a uranium compound, adding the dibenzoyl peroxide and the uranium compound into a mold according to a material ratio of 8: (0-10), and stirring until the color is uniform and does not change any more; 2, isobutyl methacrylate is added, the material proportion meets the requirement that the ratio of dibenzoyl peroxide to isobutyl methacrylate is (1-2): 1, full stirring is conducted, and then standing is conducted till the materials are cured; and 3, opening the mold and taking out the composite nuclear radiation shielding material. The invention further provides the resin-based composite nuclear radiation shielding material containing the uranium compound. By adding the uranium compound, the resin-based composite nuclear radiation shielding material has a good shielding effect on gamma rays.

Description

Technical Field

[0001] This invention relates to the field of nuclear radiation shielding materials, and in particular to a resin-based composite nuclear radiation shielding material containing uranium compounds and its preparation method. Background Technology

[0002] With the development of nuclear science and technology, mobile nuclear reactors and various radioactive materials are widely used in energy, national defense, aerospace, medicine, and industry. However, nuclear reactions typically release neutrons and gamma rays, the hazards of which to humans, the environment, and electronic equipment cannot be underestimated. Traditional nuclear shielding materials commonly use heavy metals such as lead and tungsten and their alloys, which cannot meet the requirements for nuclear radiation shielding in complex radiation fields and the weight reduction requirements of shielding materials in mobile nuclear reactors. To address the need for high-performance, lightweight shielding materials, the concept of resin-based composite nuclear radiation shielding materials has been proposed, and related research has been conducted.

[0003] Resin-based composite nuclear radiation shielding materials use resin materials rich in hydrogen, which has a strong ability to moderate and absorb neutrons, as the matrix, and add elements such as samarium and gadolinium. For example, the Institute of Nuclear Energy Safety, Hefei Institutes of Physical Science, Chinese Academy of Sciences, developed a samarium-containing epoxy resin neutron shielding material. This material was prepared by chemically modifying Sm2O3 particles with APTES and physically blending them with a high-temperature resistant epoxy resin matrix, AFG-90H, to produce a composite neutron shielding material with high thermal stability, Sm2O3-APTES / AFG-90H (Hongqing Wang, Quinying Huang, Yutao Zhai. Polymers. 2022, 14:638.). Harbin Engineering University developed a phthalonitrile-benzoxazine and tetraaminophthalocyanine lead-based radiation-resistant composite material. This material has excellent gamma-ray irradiation resistance but lacks nuclear radiation shielding capability (Chinese Patent CN201710724592.5). Harbin Engineering University has also developed radiation shielding materials based on benzoxazine, phthalonitrile, and metal boride, which also have a certain neutron shielding capability (Chinese Patent CN201710725998.5).

[0004] Boron is a commonly used neutron absorbing material, and there are many records of composite shielding materials with added boron, such as Chinese patents CN201210570726.X, CN202010932130.4, 202110345724.X, and CN202011059618.7. This shows that boron is a good additive material, but the composite nuclear radiation shielding materials disclosed in these patents do not have good gamma ray shielding capabilities.

[0005] Uranium is an excellent shielding material for gamma rays. CNNC Northern Nuclear Fuel Element Co., Ltd. has developed a processing method for depleted uranium shielding bodies, comprising the following steps: Step 1: First scribing of the ingot surface; Step 2: First rough machining of the ingot; Step 3: Second scribing of the ingot surface; Step 4: Second rough machining of the ingot; Step 5: Semi-finishing of the ingot; Step 6: Finishing of the ingot. This method can complete the milling of different types of shielding bodies, and the dimensional and positional tolerances and surface roughness of the processed products meet the product technical requirements (Chinese Patent CN201811591640.9). CNNC Northern Nuclear Fuel Element Co., Ltd. has also developed a uranium-based neutron-gamma composite shielding material. This material consists of a uranium matrix with added gadolinium (0.1–2 wt%), which is uniformly dispersed in the uranium matrix to form a dispersed composite material. This material is prepared using a vacuum melting method (Chinese Patent CN202011625306.8). The nuclear radiation shielding materials disclosed in these patents have good gamma ray shielding performance, but do not meet the weight reduction requirements of shielding materials for mobile nuclear reactors.

[0006] In summary, existing resin-based composite nuclear radiation shielding materials have high shielding performance against neutrons, but their preparation methods are not simple, and their shielding performance against gamma rays is somewhat lacking. How to improve the shielding performance of composite nuclear radiation shielding materials against gamma rays while maintaining good neutron shielding performance is a technical problem that urgently needs to be solved in this field. Summary of the Invention

[0007] The purpose of this invention is to provide a resin-based composite nuclear radiation shielding material containing uranium compounds and its preparation method, thereby solving the problem that the gamma-ray shielding effect of resin-based composite nuclear radiation shielding materials is not ideal.

[0008] To achieve the above objectives, the present invention provides the following technical solution:

[0009] A method for preparing a resin-based composite nuclear radiation shielding material containing uranium compounds, comprising:

[0010] Step 1: Weigh out benzoyl peroxide and uranium compound and add them to the mold. The material ratio should be benzoyl peroxide: uranium compound = 8: 0-10. Stir until the color is uniform and no longer changes.

[0011] Step 2: Add isobutyl methacrylate, with the material ratio satisfying benzoyl peroxide:isobutyl methacrylate = 1~2:1 (when the units of benzoyl peroxide are g or kg, the units of isobutyl methacrylate are mL or L), stir thoroughly, and then let stand until the material solidifies;

[0012] Step 3: Open the mold and remove the composite nuclear radiation shielding material.

[0013] In step 1, boron compound is weighed and added to the mold, with the material ratio satisfying benzoyl peroxide: uranium compound: boron compound = 8:0~10:0~10.

[0014] Furthermore, boron compounds contain 10 A mixture of one or more boron-containing compounds such as boron carbide, boron nitride, or zirconium boride, which are B isotopes.

[0015] Further, weigh 18 parts of benzoyl peroxide, 1 part of UO2, and 1 part of ZrB2 and add them to the mold. Stir for 90–150 seconds until the color is uniform and no longer changes. Add 18 parts of isobutyl methacrylate and stir continuously for 200–400 seconds. Wait 12–30 hours for the material to solidify. Open the mold and remove the sample. Grind the upper end of the composite nuclear radiation shielding material with silicon carbide sandpaper. The density of the obtained composite nuclear radiation shielding material is 1.12 g / cm³. 3 .

[0016] Furthermore, the boron compound has a particle size of less than 250 micrometers.

[0017] In step 1, the uranium compound is one or a mixture of several of uranium dioxide, uranium trioxide, uranium trisilicon dioxide, or uranium nitride.

[0018] Furthermore, the particle size of uranium compounds is less than 250 micrometers.

[0019] Further, 36 parts of benzoyl peroxide and 5 parts of UO2 were weighed and added to the mold, and stirred for 25-60 seconds until the color was uniform and no longer changed; 25 parts of isobutyl methacrylate were added, and stirred continuously for 25-60 seconds, and waited for 18-25 minutes until the material solidified; the mold was opened and the sample was removed, and the upper end of the composite nuclear radiation shielding material was smoothed with silicon carbide sandpaper. The density of the obtained composite nuclear radiation shielding material was 1.13 g / cm³. 3 .

[0020] The preparation method of the uranium-containing compound resin-based composite nuclear radiation shielding material further includes step 4: polishing the surface of the composite nuclear radiation shielding material with silicon carbide sandpaper.

[0021] Furthermore, the present invention also provides a resin-based composite nuclear radiation shielding material containing uranium compounds prepared by the aforementioned preparation method. The composite nuclear radiation shielding material is composed of a resin formed by the condensation of benzoyl peroxide and isobutyl methacrylate, a uranium compound, and a boron compound. The resin formed by the condensation of benzoyl peroxide and isobutyl methacrylate constitutes the matrix of the nuclear radiation shielding material, and the uranium compound and boron compound constitute the nuclear radiation shielding enhancement additive.

[0022] Compared with the prior art, the resin-based composite nuclear radiation shielding material containing uranium compounds and its preparation method provided by the present invention have the following beneficial effects:

[0023] This invention achieves excellent gamma-ray shielding effect in resin-based composite nuclear radiation shielding materials by adding uranium compounds.

[0024] This invention prepares resin-based composite nuclear radiation shielding materials by mixing benzoyl peroxide and isobutyl methacrylate. The steps are simple, the process is easy to control, and it is possible to prepare resin-based composite nuclear radiation shielding materials with complex shapes.

[0025] Furthermore, by adding boron compounds, a resin-based composite nuclear radiation shielding material was achieved that simultaneously provides excellent shielding against neutrons and gamma rays.

[0026] Furthermore, this invention simultaneously adds uranium compounds and boron compounds to the resin matrix to improve the neutron and gamma ray shielding performance of the resin-based composite nuclear radiation shielding material, which can meet the shielding requirements of mobile nuclear reactors and various radioactive materials. Attached Figure Description

[0027] To more clearly illustrate the technical solution of the present invention, the accompanying drawings used in the technical description will be briefly introduced below.

[0028] Figure 1 A schematic diagram comparing the gamma-ray shielding effects of the composite nuclear radiation shielding material provided by this invention with those of graphite and boron carbide under the same thickness conditions. Detailed Implementation

[0029] The following detailed description provides further details on specific implementation methods.

[0030] This invention provides a method for preparing a resin-based composite nuclear radiation shielding material containing uranium compounds, comprising the following steps:

[0031] Step 1: Weigh out benzoyl peroxide, uranium compound, and boron compound and add them to the mold. The material ratio should be benzoyl peroxide (g): uranium compound (g): boron compound (g) = 8: (0-10): (0-10). Stir for 30-300 seconds until the color is uniform and no longer changes.

[0032] Step 2: Add isobutyl methacrylate, with the material ratio satisfying benzoyl peroxide (g): isobutyl methacrylate (mL) = (1~2):1, stir for 30~300 seconds, and then wait for 20 minutes to 24 hours until the material cures;

[0033] Step 3: Open the mold and remove the composite nuclear radiation shielding material;

[0034] Step 4: Polish the surface of the composite nuclear radiation shielding material with silicon carbide sandpaper.

[0035] A resin-based composite nuclear radiation shielding material containing uranium compounds was prepared by the above preparation method. The composite nuclear radiation shielding material is composed of a resin formed by the condensation of benzoyl peroxide and isobutyl methacrylate, uranium compounds, and boron compounds. The resin formed by the condensation of benzoyl peroxide and isobutyl methacrylate constitutes the matrix of the nuclear radiation shielding material, and the uranium compounds and boron compounds constitute the nuclear radiation shielding enhancement additives.

[0036] Example 1

[0037] In a fume hood, weigh 7.2g of benzoyl peroxide and 0.8g of UO2 and add them to the mold. Stir for 30 seconds until the color is uniform and no longer changes (brown).

[0038] Add 5 mL of isobutyl methacrylate and stir continuously for 30 seconds.

[0039] Wait 20 minutes for the material to solidify, open the mold and take out the sample. Smooth the upper end of the composite nuclear radiation shielding material with silicon carbide sandpaper, and then number the sample.

[0040] Density measurements show that the density of the composite nuclear radiation shielding material prepared in this embodiment is 1.13 g / cm³. 3 .

[0041] Gamma-ray shielding performance test:

[0042] The conditions were as follows: an Am-241 gamma source (source strength 50 mCi) was used, the detector was a Φ20 mm BGO, the source-detector distance was 90 mm, the collimation aperture was Φ5.6 mm, the measurement time was 30 s, the zero point was 2223780, and the background was 2175. The test was repeated 5 times, with counts of 1310846, 1309747, 1301369, 1309870, and 1309203 respectively. Based on this, the linear attenuation coefficient of the composite nuclear radiation shielding material prepared in this embodiment for gamma rays was calculated to be 0.02592.

[0043] The shielding capabilities of graphite and B4C against gamma rays were tested under the same conditions. The calculated linear attenuation coefficients were 0.02365 for graphite and 0.02178 for B4C. A comparison of the linear attenuation coefficients is shown in the figure below. Figure 1 (Sample No. 1). It is evident that, under the same thickness conditions, the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment exhibits improved gamma-ray shielding capability compared to commonly used neutron shielding materials such as graphite and B4C. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is further advantageous.3 ) and B4C (approximately 2.52 g / cm³) 3 This material has a more outstanding gamma-ray shielding ability and also has a good effect on reducing the weight of shielding materials.

[0044] Thermal neutron shielding performance simulation:

[0045] Monte Carlo simulations were performed on the thermal neutron shielding performance of the uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment. The number of 0.5 eV thermal neutrons passing through a 1 mm thick material was calculated, and the shielding performance of different materials was compared. The Monte Carlo simulation results show that after 0.5 eV thermal neutrons pass through a 1 mm thick uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment, the total number of neutrons decreases to 8.83E-03.

[0046] Under the same simulation conditions, the total number of neutrons decreased to 8.80E-03 after passing through a 1 mm thick layer of graphite with a 0.5 eV energy. This demonstrates that, under the same thickness conditions, the thermal neutron shielding performance of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is comparable to that of graphite. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is a significant improvement. 3 This material has better thermal neutron shielding capabilities and also plays a significant role in reducing the weight of shielding materials.

[0047] Therefore, in this embodiment, the uranium-containing compound-based resin-based composite nuclear radiation shielding material has good gamma-ray shielding capability and thermal neutron shielding capability.

[0048] Example 2

[0049] In a fume hood, weigh 7.2g benzoyl peroxide, 0.6g UO2, and 0.2g ZrB2 and add them to the mold. Stir for 180 seconds until the color is uniform and no longer changes (brown).

[0050] Add 3.6 mL of isobutyl methacrylate and stir continuously for 90 seconds.

[0051] Wait 60 minutes for the material to solidify, open the mold and take out the sample. Smooth the upper end of the composite nuclear radiation shielding material with silicon carbide sandpaper, and then number the sample.

[0052] Density measurements show that the density of the composite nuclear radiation shielding material prepared in this embodiment is 1.13 g / cm³. 3 .

[0053] Gamma-ray shielding performance test:

[0054] The conditions were as follows: an Am-241 gamma source (source strength 50 mCi) was used, the detector was a Φ20 mm BGO, the distance between the source and detector was 90 mm, the collimation aperture was Φ5.6 mm, the measurement time was 30 s, the zero point was 2223780, and the background was 2175. The test was repeated 5 times, with counts of 960864, ​​959081, 958337, 958471, and 961010 respectively. Based on this, the linear attenuation coefficient of the composite nuclear radiation shielding material prepared in this embodiment for gamma rays was calculated to be 0.03557.

[0055] The shielding capabilities of graphite and B4C against gamma rays were tested under the same conditions. The calculated linear attenuation coefficients were 0.02365 for graphite and 0.02178 for B4C. A comparison of the linear attenuation coefficients is shown in the figure below. Figure 1 (Sample No. 2). It is evident that, under the same thickness conditions, the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment exhibits improved gamma-ray shielding capability compared to commonly used neutron shielding materials such as graphite and B4C. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is further advantageous. 3 ) and B4C (approximately 2.52 g / cm³) 3 This material has a more outstanding gamma-ray shielding ability and also has a good effect on reducing the weight of shielding materials.

[0056] Thermal neutron shielding performance simulation:

[0057] Monte Carlo simulations were performed on the thermal neutron shielding performance of the uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment. The number of 0.5 eV thermal neutrons passing through a 1 mm thick material was calculated, and the shielding performance of different materials was compared. The Monte Carlo simulation results show that after 0.5 eV thermal neutrons pass through a 1 mm thick uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment, the total number of neutrons decreases to 8.70E-03.

[0058] Under the same simulation conditions, the total number of neutrons decreased to 8.80E-03 after passing through a 1 mm thick layer of graphite with a 0.5 eV energy. This demonstrates that, under the same thickness conditions, the thermal neutron shielding performance of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is comparable to that of graphite. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is a significant improvement. 3 This material has better thermal neutron shielding capabilities and also plays a significant role in reducing the weight of shielding materials.

[0059] Therefore, in this embodiment, the uranium-containing compound-based resin-based composite nuclear radiation shielding material has good gamma-ray shielding capability and thermal neutron shielding capability.

[0060] Example 3

[0061] In a fume hood, weigh 7.2g benzoyl peroxide, 0.4g UO2, and 0.4g ZrB2 and add them to the mold. Stir for 120 seconds until the color is uniform and no longer changes (brown).

[0062] Add 7.2 mL of isobutyl methacrylate and stir continuously for 300 seconds.

[0063] Wait 24 hours for the material to cure, open the mold and take out the sample. Smooth the upper end of the composite nuclear radiation shielding material with silicon carbide sandpaper, and then number the sample.

[0064] Density measurements show that the density of the composite nuclear radiation shielding material prepared in this embodiment is 1.12 g / cm³. 3 .

[0065] Gamma-ray shielding performance test:

[0066] The conditions were as follows: an Am-241 gamma source (source strength 50 mCi) was used, the detector was a Φ20 mm BGO, the distance between the source and detector was 90 mm, the collimation aperture was Φ5.6 mm, the measurement time was 30 s, the zero point was 2223780, and the background was 2175. The test was repeated 5 times, and the counts were 1091192, 1091122, 1090730, 1089629, and 1092019, respectively. Based on this, the linear attenuation coefficient of the composite nuclear radiation shielding material prepared in this embodiment for gamma rays was calculated to be 0.03187.

[0067] The shielding capabilities of graphite and B4C against gamma rays were tested under the same conditions. The calculated linear attenuation coefficients were 0.02365 for graphite and 0.02178 for B4C. A comparison of the linear attenuation coefficients is shown in the figure below. Figure 1 (Sample No. 3). It is evident that, under the same thickness conditions, the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment exhibits improved gamma-ray shielding capability compared to commonly used neutron shielding materials such as graphite and B4C. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is further advantageous. 3 ) and B4C (approximately 2.52 g / cm³) 3 This material has a more outstanding gamma-ray shielding ability and also has a good effect on reducing the weight of shielding materials.

[0068] Thermal neutron shielding performance simulation:

[0069] Monte Carlo simulations were performed on the thermal neutron shielding performance of the uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment. The number of 0.5 eV thermal neutrons passing through a 1 mm thick material was calculated, and the shielding performance of different materials was compared. The Monte Carlo simulation results show that after 0.5 eV thermal neutrons pass through a 1 mm thick uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment, the total number of neutrons decreases to 8.57E-03.

[0070] Under the same simulation conditions, the total number of neutrons decreased to 8.80E-03 after passing through a 1 mm thick layer of graphite with a 0.5 eV energy. This demonstrates that, under the same thickness conditions, the thermal neutron shielding performance of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is comparable to that of graphite. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is a significant improvement. 3 This material has better thermal neutron shielding capabilities and also plays a significant role in reducing the weight of shielding materials.

[0071] Therefore, in this embodiment, the uranium-containing compound-based resin-based composite nuclear radiation shielding material has good gamma-ray shielding capability and thermal neutron shielding capability.

[0072] Example 4

[0073] In a fume hood, weigh 7.2g benzoyl peroxide, 0.2g UO2, and 0.6g ZrB2 and add them to the mold. Stir for 300 seconds until the color is uniform and no longer changes (brown).

[0074] Add 5 mL of isobutyl methacrylate and stir continuously for 30 seconds.

[0075] Wait 15 hours for the material to cure, open the mold and take out the sample. Smooth the upper end of the composite nuclear radiation shielding material with silicon carbide sandpaper, and then number the sample.

[0076] Density measurements show that the density of the composite nuclear radiation shielding material prepared in this embodiment is 1.12 g / cm³. 3 .

[0077] Gamma-ray shielding performance test:

[0078] The conditions were as follows: an Am-241 gamma source (source strength 50 mCi) was used, the detector was a Φ20 mm BGO, the distance between the source and detector was 90 mm, the collimation aperture was Φ5.6 mm, the measurement time was 30 s, the zero point was 2223780, and the background was 2175. The test was repeated 5 times, with counts of 1226659, 1224170, 1226309, 1225365, and 1224424 respectively. Based on this, the linear attenuation coefficient of the composite nuclear radiation shielding material prepared in this embodiment for gamma rays was calculated to be 0.03187.

[0079] The shielding capabilities of graphite and B4C against gamma rays were tested under the same conditions. The calculated linear attenuation coefficients were 0.02365 for graphite and 0.02724 for B4C. A comparison of the linear attenuation coefficients is shown in the figure below. Figure 1 (Sample No. 4). It is evident that, under the same thickness conditions, the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment exhibits improved gamma-ray shielding capability compared to commonly used neutron shielding materials such as graphite and B4C. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is further advantageous. 3 ) and B4C (approximately 2.52 g / cm³) 3 This material has a more outstanding gamma-ray shielding ability and also has a good effect on reducing the weight of shielding materials.

[0080] Thermal neutron shielding performance simulation:

[0081] Monte Carlo simulations were performed on the thermal neutron shielding performance of the uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment. The number of 0.5 eV thermal neutrons passing through a 1 mm thick material was calculated, and the shielding performance of different materials was compared. The Monte Carlo simulation results show that after 0.5 eV thermal neutrons pass through a 1 mm thick uranium-containing compound resin-based composite nuclear radiation shielding material prepared in this embodiment, the total number of neutrons decreases to 8.44E-03.

[0082] Under the same simulation conditions, the total number of neutrons decreased to 8.80E-03 after passing through a 1 mm thick layer of graphite with a 0.5 eV energy. This demonstrates that, under the same thickness conditions, the thermal neutron shielding performance of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is comparable to that of graphite. Considering that the density of the uranium-containing resin-based composite nuclear radiation shielding material prepared in this embodiment is much lower than that of graphite (1.6–2.0 g / cm³), this is a significant improvement. 3 This material has better thermal neutron shielding capabilities and also plays a significant role in reducing the weight of shielding materials.

[0083] Therefore, in this embodiment, the uranium-containing compound-based resin-based composite nuclear radiation shielding material has good gamma-ray shielding capability and thermal neutron shielding capability.

[0084] The above description is merely a specific embodiment of the present invention, but the scope of protection of the present invention is not limited thereto. Any variations or substitutions that can be easily conceived by those skilled in the art within the technical scope disclosed in the present invention should be included within the scope of protection of the present invention. Therefore, the scope of protection of the present invention should be determined by the scope of the claims.

Claims

1. A method for preparing a resin-based composite nuclear radiation shielding material containing uranium compounds, characterized in that, include: Step 1: Weigh out benzoyl peroxide and uranium compound and add them to the mold. The material ratio should be benzoyl peroxide: uranium compound = 8: 0-10. Stir until the color is uniform and no longer changes. Step 2: Add isobutyl methacrylate, ensuring the material ratio is benzoyl peroxide:isobutyl methacrylate = 1~2:1, stir thoroughly, and then let stand until the material solidifies; Step 3: Open the mold and remove the composite nuclear radiation shielding material.

2. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 1, characterized in that, In step 1, boron compound is weighed and added to the mold, with the material ratio satisfying benzoyl peroxide: uranium compound: boron compound = 8:0~10:0~10.

3. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 2, characterized in that, Boron compounds are those containing 10 A mixture of one or more boron-containing compounds such as boron carbide, boron nitride, or zirconium boride, which are B isotopes.

4. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 2 or 3, characterized in that, Weigh out 18 parts of benzoyl peroxide, 1 part of UO2, and 1 part of ZrB2 and add them to a mold. Stir for 90–150 seconds until the color is uniform and no longer changes. Add 18 parts of isobutyl methacrylate and stir continuously for 200–400 seconds. Wait 12–30 hours for the material to solidify. Open the mold and remove the sample. Grind the upper end of the composite nuclear radiation shielding material with silicon carbide sandpaper. The density of the obtained composite nuclear radiation shielding material is 1.12 g / cm³. 3 .

5. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 2, characterized in that, Boron compounds have a particle size of less than 250 micrometers.

6. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 1, characterized in that, In step 1, the uranium compound is one or a mixture of several of uranium dioxide, uranium trioxide, uranium trisilicon dioxide, or uranium nitride.

7. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 1, characterized in that, Uranium compounds have a particle size of less than 250 micrometers.

8. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 1, characterized in that, Weigh 36 parts of benzoyl peroxide and 5 parts of UO2 and add them to the mold. Stir for 25-60 seconds until the color is uniform and no longer changes. Add 25 parts of isobutyl methacrylate and stir continuously for 25-60 seconds. Wait 18-25 minutes until the material solidifies. Open the mold and remove the sample. Grind the upper end of the composite nuclear radiation shielding material with silicon carbide sandpaper. The density of the obtained composite nuclear radiation shielding material is 1.13 g / cm³. 3 .

9. The method for preparing the resin-based composite nuclear radiation shielding material containing uranium compounds according to claim 1, characterized in that, It also includes step 4: sanding the surface of the composite nuclear radiation shielding material with silicon carbide sandpaper.

10. A resin-based composite nuclear radiation shielding material containing uranium compounds prepared by the preparation method according to any one of claims 1 to 9, characterized in that, The material is composed of a resin formed by the condensation of benzoyl peroxide and isobutyl methacrylate, uranium compounds, and boron compounds. The resin formed by the condensation of benzoyl peroxide and isobutyl methacrylate constitutes the matrix of the nuclear radiation shielding material, while the uranium compounds and boron compounds constitute the nuclear radiation shielding enhancement additives.

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