Nuclear radiation protection concrete and preparation method thereof

Abstract

This application relates to the technical field of concrete and specifically discloses a nuclear radiation protection concrete and its preparation method. The nuclear radiation protection concrete disclosed in this application comprises the following components: cement, a radiation protection agent, barite sand, crushed stone, silica fume, a retarder, a polycarboxylic acid water reducer, a defoamer, a thickener, an admixture, and water. The radiation protection agent is prepared by uniformly mixing barium powder, borosilicate glass, castor oil polyoxyethylene ether, and ethanol in a weight ratio of (20-28): (48-54): (5-10): 20, heating the mixture to 1200-1350°C at a heating rate of 5-10°C / min and holding the mixture at that temperature for 1-2 hours; then quenching the mixture with water, drying, ball milling, and sieving to obtain a radiation protection agent with a particle size of ≤200 mesh. This application also discloses a preparation method for the nuclear radiation protection concrete. The nuclear radiation protection concrete disclosed in this application has good radiation protection effects and can also improve the mechanical properties and frost resistance of the concrete.

Description

Technical Field

[0001] The present application relates to the technical field of concrete, and in particular to a nuclear radiation protection concrete and a preparation method thereof. Background Art

[0002] Concrete is an essential material in the construction industry. With the development of concrete technology and the expansion of its application needs, various new types of concrete have emerged, including high-strength concrete, nuclear radiation-resistant concrete, and pumpable concrete.

[0003] However, while concrete meets basic engineering needs, it also suffers from a single function, making it inadequate for specialized projects. With the continuous development of society and the economy, higher demands are being placed on concrete's additional functions. In particular, the growing use of various radiation-related equipment in the medical industry has placed new demands on concrete's radiation protection capabilities.

[0004] The current nuclear radiation protection concrete uses high-density materials as aggregates, which have workability problems such as poor fluidity, easy water seepage, and segregation, resulting in poor concrete construction performance. The prepared concrete has poor frost resistance, is prone to cracking, and lacks durability. Summary of the Invention

[0005] In order to improve the fluidity and frost resistance of nuclear radiation protection concrete, the present application provides a nuclear radiation protection concrete and a preparation method thereof.

[0006] In a first aspect, the present application provides a nuclear radiation protection concrete, specifically comprising the following components in parts by weight: 240-280 parts of cement, 60-80 parts of radiation shielding agent, 165-185 parts of barite sand, 510-550 parts of crushed stone, 120-160 parts of silica fume, 3-8 parts of retarder, 4-6 parts of polycarboxylate water reducer, 1-2 parts of defoamer, 0.2-0.6 parts of thickener, 2-8 parts of admixture, and 100-130 parts of water;

[0007] The preparation method of the radiation shielding agent comprises the following steps: uniformly mixing barium powder, borosilicate glass, castor oil polyoxyethylene ether and ethanol in a weight ratio of (20-28): (48-54): (5-10): 20; heating the mixture to 1200-1350°C at a heating rate of 5-10°C / min and keeping the temperature for 1-2 hours; and then water quenching, drying and ball milling to obtain a radiation shielding agent with a particle size of ≤200 mesh.

[0008] The barium element in barium powder effectively shields various radiation rays, and borosilicate glass mineral admixtures containing boron can absorb large quantities of slow neutrons, thereby effectively shielding against neutron rays. The inventors of this application discovered that using castor oil polyoxyethylene ether as a blending agent for barium powder and borosilicate glass, mixed with ethanol as a solvent, can stimulate the silicon-oxygen chains and boron-oxygen bonds in the borosilicate glass to effectively collide with barium powder particles, generating long, fine, fibrous interparticle bonds and forming a micronetwork structure. This, when applied to concrete, effectively prevents the radiation-blocking powder from sinking, resolving the problem of high-density radiation-blocking powders being unable to maintain stable suspension and sinking too quickly during concrete mixing. This allows the radiation-blocking agent powder to be evenly distributed within the concrete system, ensuring the density of the slurry. That is, the nuclear radiation protection concrete provided by this application contains shielding elements with good radiation protection functions. It can not only effectively shield various rays generated during the application of nuclear technology, but also effectively slow down neutrons, realize multi-element shielding, reduce radiation hazards, and have excellent radiation protection performance; and can compensate for the micro-expansion of cement hydration volume, effectively prevent the formation of micro-cracks inside the concrete, increase the density of the two, and effectively achieve shielding against β, α, γ rays and neutrons.

[0009] At the same time, the present application optimizes the components and ratios of barium powder, borosilicate glass, and castor oil polyoxyethylene ether in the radiation shielding agent, so that the radiation shielding agent is added to concrete to form a material that is approximately a continuum, thereby improving the compatibility with the concrete base material system, thereby reducing the impact on the physical properties of the base material, maintaining the physical properties of the base material itself and imparting new radiation protection functions, while giving the nuclear radiation protection concrete higher fluidity.

[0010] In addition, the radiation shielding agent of the present application provides a large amount of silica through a high dosage of mineral admixtures. When combined with the silica fume in the concrete formula, it can undergo a secondary hydration reaction with the cement hydration products, thereby improving the strength and durability of the concrete. At the same time, it makes the concrete have good adsorption and water retention, which can effectively reduce the free water content in the concrete mixture and reduce the water-cement ratio, thereby effectively improving the frost resistance of the concrete. The present application uses baryte sand of a certain particle size to reduce the density difference between the powder and the aggregate, reduce the sedimentation of the aggregate in the slurry, and thus achieve high fluidity, anti-segregation, and self-compacting properties of the concrete. At the same time, it increases the density of the concrete, improves the frost resistance and crack resistance of the concrete, and the baryte sand also has a radiation shielding effect.

[0011] Preferably, 250-270 parts of cement, 65-75 parts of radiation shielding agent, 170-180 parts of barite sand, 520-540 parts of crushed stone, 130-150 parts of silica fume, 4-6 parts of retarder, 4-6 parts of polycarboxylate water reducer, 1-2 parts of defoaming agent, 0.2-0.6 parts of thickener, 4-6 parts of admixture, and 115-125 parts of water.

[0012] Optionally, the weight ratio of the barium powder, the borosilicate glass, the castor oil polyoxyethylene ether and the ethanol is (25-28): (48-50): (6-8): 20.

[0013] Optionally, the barium powder is selected from any one or more of barium oxide and barium sulfate.

[0014] Optionally, the saponification value of the castor oil polyoxyethylene ether is 70-100 mgKOH / g.

[0015] Optionally, the barite sand is medium sand with a fineness modulus of 2.3-2.5 and a barium sulfate content of ≥80%.

[0016] Optionally, the silica fume is silica powder with a specific surface area of ​​25-35m 2 / g.

[0017] Optionally, the crushed stone is 2-10 mm granite crushed stone with an apparent density of 2300-2800 kg / m 3 .

[0018] The density of nuclear radiation protection concrete structures directly affects the shielding effect of the concrete; the denser the structure, the better the shielding effect. A reasonable aggregate gradation distribution can effectively improve the density of the concrete structure. This application utilizes barite sand, silica fume, and crushed stone with the aforementioned specifications as the raw material components of the concrete. This facilitates the filling of fine aggregate into the pores formed by the coarse aggregate, thereby increasing the density of the concrete. While maintaining the mechanical properties of the concrete, it also improves the concrete's shielding performance against β, α, and γ rays, as well as neutrons.

[0019] Optionally, the admixture is sorbitol and polyethylene glycol in a weight ratio of 15:(1-3).

[0020] Optionally, the molecular weight of the polyethylene glycol is 2000-6000.

[0021] The present application utilizes sorbitol and polyethylene glycol in the above-mentioned weight ratio as admixtures, and greatly improves the fluidity of nuclear radiation protection concrete through the high dispersion and surface modification effects of the admixtures; under the action of the admixtures, the consistency and viscosity of the concrete mixture can be regulated according to actual needs, which can also ensure the homogeneity of the concrete system, improve the frost resistance and crack resistance of the concrete, and thus ensure the durability of the concrete.

[0022] In a second aspect, the present application provides a method for preparing the above-mentioned nuclear radiation protection concrete, which specifically comprises the following steps: weighing the cement, the barite sand, and the stone in parts by weight, and stirring and mixing them uniformly to obtain a dry material;

[0023] The radiation shielding agent is added to one-half of the water, stirred and mixed evenly, and then added to the dry material to obtain a premix; the retarder, the polycarboxylate water-reducing agent, the defoamer, the thickener, and the admixture are weighed by weight and added to the remaining water to form a liquid material;

[0024] The liquid material is added to the premix and stirred evenly to obtain the nuclear radiation protection concrete.

[0025] In summary, the technical solution of this application has the following effects:

[0026] The present application prepares a radiation protection agent by using barium powder, borosilicate glass, castor oil polyoxyethylene ether and ethanol in a suitable ratio. The obtained nuclear radiation protection concrete can effectively block gamma particles and neutron particles from passing through the concrete wall, thereby improving the radiation protection performance of the concrete; and the concrete prepared in the present application has good fluidity and frost resistance.

[0027] This application further improves the radiation protection performance of concrete by optimizing the dosage and specification parameters of various raw materials in concrete, while ensuring that the concrete has high frost resistance and improving the durability of concrete. DETAILED DESCRIPTION

[0028] The present application is further described in detail below in conjunction with examples, comparative examples and performance testing experiments. These examples should not be construed as limiting the scope of protection claimed in this application.

[0029] Borosilicate glass (particle size of 0.4-0.6 mm) was purchased from Luoyang Tengjing Glass Co., Ltd.; castor oil polyoxyethylene ether and fatty amine polyoxyethylene ether were purchased from Hai'an Petrochemical Plant in Jiangsu Province; barite sand was purchased from Shandong Motor Metal Materials Co., Ltd.; polycarboxylic acid water reducer (model TD-JSS) was purchased from Tuoda (Shandong) New Materials Technology Industry Group Co., Ltd.; defoamer (model XWC-0285 powder / T112) was purchased from Hefei Xinwancheng Environmental Protection Technology Co., Ltd., and thickener (model Rheovis PU 1190) was purchased from Chongqing Pingchuan Chemical Co., Ltd.; the remaining raw materials can be obtained commercially.

[0030] Example

[0031] Examples 1-7

[0032] Examples 1-7 each provide a nuclear radiation protection concrete.

[0033] The difference between the above embodiments is that the dosage of each component in the radiation protection agent is different, as shown in Table 1.

[0034] The preparation method of the radiation shielding agent in the above embodiment is:

[0035] According to Table 1, barium oxide, borosilicate glass, castor oil polyoxyethylene ether (specification EL-30, saponification value 70-80 mgKOH / g), and ethanol were weighed in corresponding parts by weight and placed in a dry alumina crucible and evenly mixed. The mixture was heated to 1300°C at a heating rate of 8°C / min and kept warm for 1.5 hours; then quenched with cold water, and the quenched material was placed in a 160°C oven and dried for 4 hours. It was then ball-milled in a ceramic jar with alcohol for 30 minutes and passed through a 200-mesh sieve to obtain a radiation shield with a particle size of ≤200 mesh.

[0036] Table 1 Amount of each component in the radiation protection agent in Examples 1-7

[0037]

[0038] The preparation method of the nuclear radiation protection concrete in the above embodiment is:

[0039] Weigh 260g PO 22.5 ordinary Portland cement, 175g barite sand (medium sand, fineness modulus 2.3-2.5, barium sulfate content ≥80%), 530g crushed stone (crushed stone is 2-10mm granite crushed stone, apparent density 2300-2800kg / m 3 ), stirring and mixing to obtain dry material;

[0040] Mix 70g of radiation protection agent and 140g of silica fume (silica fume is silicon powder with a specific surface area of ​​30±3m 2 / g) was added to 60 g of water, stirred and mixed evenly, and added to the dry material to obtain a premix;

[0041] Weigh 5 g of retarder (a mixture of sodium gluconate and sodium tripolyphosphate in a weight ratio of 5:3), 5 g of polycarboxylic acid water reducer, 1.5 g of defoamer, 0.4 g of thickener, and 5 g of admixture (a mixture of sorbitol and polyethylene glycol PEG-4000 in a weight ratio of 15:2) by weight, and add them to the remaining 60 g of water to form a liquid material;

[0042] Add the liquid material to the premix and stir evenly to obtain nuclear radiation protection concrete.

[0043] Examples 8-11

[0044] Examples 8-11 each provide a nuclear radiation protection concrete.

[0045] The difference between the above embodiment and embodiment 2 is that the types of components in the radiation protection agent are different, specifically: in embodiment 8, an equal amount of barium sulfate is used instead of barium oxide.

[0046] In Example 9, the specification of castor oil polyoxyethylene ether is EL-12, and the saponification value is 110-120 mgKOH / g.

[0047] In Example 10, the specification of castor oil polyoxyethylene ether is EL-20, and the saponification value is 90-100 mgKOH / g.

[0048] In Example 11, the specification of castor oil polyoxyethylene ether is EL-40, and the saponification value is 57-67 mgKOH / g.

[0049] The preparation method of the radiation shielding agent, other raw materials and their amounts, and the preparation method of the nuclear radiation protection concrete in the above embodiment are the same as those in Example 2.

[0050] Examples 12-21

[0051] Examples 12-21 each provide a nuclear radiation protection concrete.

[0052] The difference between the above embodiment and embodiment 2 is that the types of barite sand, silica fume and admixtures in the nuclear radiation protection concrete are different, specifically:

[0053] In Example 12, the fineness modulus of the barite sand is 2.6-2.8, and the barium sulfate content is ≥80%.

[0054] In Example 13, the fineness modulus of the barite sand is 1.9-2.2, and the barium sulfate content is ≥80%.

[0055] In Example 14, the silica fume is silica powder with a specific surface area of ​​20±3m 2 / g.

[0056] In Example 15: the admixture is sorbitol.

[0057] In Example 16: the admixture is polyethylene glycol PEG-4000.

[0058] In Example 17, the admixture is a mixture of sorbitol and polyethylene glycol PEG-6000 in a weight ratio of 15:2.

[0059] In Example 18, the admixture is a mixture of sorbitol and polyethylene glycol PEG-4000 in a weight ratio of 15:0.5.

[0060] In Example 19, the admixture is a mixture of sorbitol and polyethylene glycol PEG-4000 in a weight ratio of 15:1.

[0061] In Example 20, the admixture is a mixture of sorbitol and polyethylene glycol PEG-4000 in a weight ratio of 15:3.

[0062] In Example 21, the admixture is a mixture of sorbitol and polyethylene glycol PEG-4000 in a weight ratio of 15:3.5.

[0063] The preparation method of the radiation shielding agent, other raw materials and their amounts, and the preparation method of the nuclear radiation protection concrete in the above embodiment are the same as those in Example 2.

[0064] Examples 22-23

[0065] Examples 22-23 each provide a nuclear radiation protection concrete.

[0066] The difference between the above embodiment and embodiment 2 is that the amount of each component in the nuclear radiation protection concrete is shown in Table 2.

[0067] The preparation methods of the radiation protection agent and nuclear radiation protection concrete in the above examples are the same as those in Example 2.

[0068] Table 2 Amount of each component in nuclear radiation protection concrete

[0069]

[0070]

[0071] Comparative Example

[0072] Comparative Examples 1-3

[0073] Comparative Examples 1-3 each provide a nuclear radiation protection concrete.

[0074] The difference between the comparative example and Example 2 is that the amount of each component in the nuclear radiation protection concrete is shown in Table 2.

[0075] The preparation methods of the radiation protection agent and the nuclear radiation protection concrete in the above comparative example are the same as those in Example 2.

[0076] Comparative Examples 4-6

[0077] Comparative Examples 4-6 each provide a nuclear radiation protection concrete.

[0078] The difference between the comparative example and Example 2 is that the types of components in the radiation protection agent are different, specifically: in Comparative Example 4, an equal amount of lithium oxide is used instead of barium oxide.

[0079] In Comparative Example 5, an equal amount of quartz glass was used instead of borosilicate glass.

[0080] In Comparative Example 6, an equal amount of fatty amine polyoxyethylene ether (specification: AC-1210, total amine value: 82-92 mgKOH / g) was used to replace castor oil polyoxyethylene ether.

[0081] The preparation method of the radiation shielding agent, other raw materials and their amounts, and the preparation method of the nuclear radiation protection concrete in the comparative example are the same as those in Example 2.

[0082] Comparative Example 7

[0083] Comparative Example 7 provides a nuclear radiation protection concrete.

[0084] The difference between this comparative example and Example 2 is as follows: the preparation method of nuclear radiation protection concrete is as follows: weigh 260g PO 22.5 ordinary Portland cement, 175g barite sand (medium sand, fineness modulus of 2.3-2.5, barium sulfate content ≥80%), 530g crushed stone (crushed stone is 2-10mm granite crushed stone, apparent density of 2300-2800kg / m 3 ) and 140g silica fume (silica fume is silicon powder with a specific surface area of ​​30±3m 2 / g), stirring and mixing to obtain dry material;

[0085] Add 70g of radiation shielding agent (prepared as in Example 2) to 60g of water, stir and mix evenly, and add to the dry material to obtain a premix;

[0086] Weigh 5 g of retarder (a mixture of sodium gluconate and sodium tripolyphosphate in a weight ratio of 5:3), 5 g of polycarboxylic acid water reducer, 1.5 g of defoamer, 0.4 g of thickener, and 5 g of admixture (a mixture of sorbitol and polyethylene glycol PEG-4000 in a weight ratio of 15:2) by weight, and add them to the remaining 60 g of water to form a liquid material;

[0087] Add the liquid material to the premix and stir evenly to obtain nuclear radiation protection concrete.

[0088] The preparation method of the radiation protection agent and the dosage of the raw material components of the nuclear radiation protection concrete in this comparative example are the same as those in Example 2.

[0089] Comparative Example 8

[0090] Comparative Example 8 provides a nuclear radiation protection concrete.

[0091] The difference between this comparative example and Example 2 is as follows: the preparation method of nuclear radiation protection concrete is as follows: weigh 260g PO 22.5 ordinary Portland cement, 175g barite sand (medium sand, fineness modulus of 2.3-2.5, barium sulfate content ≥80%), 530g crushed stone (crushed stone is 2-10mm granite crushed stone, apparent density of 2300-2800kg / m 3 ) and 140g silica fume (silica fume is silicon powder with a specific surface area of ​​30±3m 2 / g) and 70g of radiation shielding agent (prepared by the same method as in Example 2), stirring and mixing to obtain a dry material;

[0092] Weigh 5 g of retarder (a mixture of sodium gluconate and sodium tripolyphosphate in a weight ratio of 5:3), 5 g of polycarboxylic acid water reducer, 1.5 g of defoamer, 0.4 g of thickener, and 5 g of admixture (a mixture of sorbitol and polyethylene glycol PEG-4000 in a weight ratio of 15:2) in parts by weight and add them to 120 g of water to form a liquid material;

[0093] Add the liquid material to the dry material and mix well to obtain nuclear radiation protection concrete.

[0094] The preparation method of the radiation protection agent and the dosage of the raw material components of the nuclear radiation protection concrete in the above comparative example are the same as those in Example 2.

[0095] Performance testing

[0096] (1) Radiation protection performance test of concrete

[0097] The linear attenuation coefficients of the concrete prepared in the examples and comparative examples were tested using the method of GB18871-2016 "Basic Standard for Ionizing Radiation Protection and Radiation Source Safety" to evaluate the radiation protection performance of the nuclear radiation protection concrete.

[0098] (2) Slump of concrete

[0099] The test is carried out in accordance with GB / T50080-2016 "Standard for Test Methods of Performance of Ordinary Concrete Mixtures".

[0100] (3) Mechanical properties of concrete

[0101] According to GB / T50081-2016 "Standard for Test Methods of Mechanical Properties of Ordinary Concrete", the compressive strength of standard test blocks after 28 days of curing is tested.

[0102] (4) Frost resistance of concrete

[0103] The prepared concrete specimens were subjected to frost resistance tests in accordance with GB / T 50082-2009, "Standard for Test Methods for Long-term Performance and Durability of Ordinary Concrete." The frost resistance test characterized the concrete specimens' frost resistance by measuring their freeze-thaw compressive strength after 28 days of standard curing and 20 freeze-thaw cycles. The compressive strength after 28 days of standard curing and before the freeze-thaw test was recorded as the initial compressive strength.

[0104] Test results: as shown in Table 3.

[0105] Table 3 Performance test results of concrete samples in Examples 1-23 and Comparative Examples 1-8

[0106]

[0107]

[0108] Combined with the test results in Table 5, by comparing the test results of Examples 1-23 with those of Comparative Examples 1-8, it can be seen that the nuclear radiation protection concrete obtained by using the formula and preparation method provided by the present application can effectively block γ particles and neutron particles from passing through the concrete wall, thereby improving the radiation protection performance of the concrete; and the concrete prepared in the present application has good fluidity and frost resistance.

[0109] By comparing the test results of Examples 2, 22-23 with those of Comparative Examples 1-3, it can be seen that the present application can effectively ensure that the concrete obtains radiation protection performance by controlling the amount of each component in the nuclear radiation protection concrete, while making the prepared concrete have good fluidity and frost resistance.

[0110] By comparing the test results of Example 2 with those of Comparative Examples 7-8, it was found that when the order of adding raw materials was changed, the radiation protection performance and mechanical properties of the prepared concrete were poor; however, the present application significantly improved the comprehensive performance of the concrete by optimizing the order of adding raw materials.

[0111] By comparing the test results of Example 2 with those of Comparative Examples 4-6, when lithium oxide is used instead of barium oxide, or quartz glass is used instead of borosilicate glass, or fatty amine polyoxyethylene ether is used instead of castor oil polyoxyethylene ether, the radiation resistance of the concrete is poor. In the present application, barium powder and borosilicate glass are combined to obtain concrete with better radiation resistance while ensuring the mechanical properties of the concrete.

[0112] By comparing Example 2 with Examples 8-11, when the present application selects barium oxide and borosilicate glass and castor oil polyoxyethylene ether with a saponification value of 70-100 mgKOH / g to cooperate with each other, the performance of nuclear radiation protection concrete can be further improved.

[0113] By comparing Example 2 with Examples 12-14, when the present application selects heavy crystal sand with a fineness modulus of 2.3-2.5 and a specific surface area of ​​25-35m 2 / g of silica fume can further improve the performance of nuclear radiation protection concrete.

[0114] By comparing the test results of Examples 2 and 15-21, the present application selects sorbitol and polyethylene glycol in a weight ratio of 15:(1-3) as admixtures, and controls the molecular weight of polyethylene glycol to be 2000-6000, which can further improve the frost resistance of nuclear radiation protection concrete and ensure the durability of concrete.

[0115] Although the present invention has been described in detail above using general descriptions and specific embodiments, it will be apparent to those skilled in the art that modifications and improvements may be made based on the present invention. Therefore, such modifications and improvements, which do not depart from the spirit of the present invention, are intended to be within the scope of protection claimed herein.

Claims

1. A nuclear radiation protection concrete, characterized in that: Specifically, it includes the following components in parts by weight: 240-280 parts of cement, 60-80 parts of radiation protection agent, 165-185 parts of barite sand, 510-550 parts of crushed stone, 120-160 parts of silica fume, 3-8 parts of retarder, 4-6 parts of polycarboxylate water reducer, 1-2 parts of defoamer, 0.2-0.6 parts of thickener, 2-8 parts of admixture, and 100-130 parts of water; the admixture is sorbitol and polyethylene glycol in a weight ratio of 15:1-3; The preparation method of the radiation shielding agent comprises the following steps: uniformly mixing barium powder, borosilicate glass, castor oil polyoxyethylene ether and ethanol in a weight ratio of (20-28): (48-54): (5-10): 20; heating the mixture to 1200-1350°C at a heating rate of 5-10°C / min and keeping the temperature for 1-2 hours; then quenching with water, drying, ball milling and sieving to obtain a radiation shielding agent with a particle size of ≤200 mesh; the barium powder is selected from any one or more of barium oxide and barium sulfate.

2. The nuclear radiation protection concrete according to claim 1, characterized in that: The weight ratio of the barium powder, the borosilicate glass, the castor oil polyoxyethylene ether and the ethanol is (25-28): (48-50): (6-8):

20.

3. The nuclear radiation protection concrete according to claim 1, characterized in that: The saponification value of the castor oil polyoxyethylene ether is 70-100 mgKOH / g.

4. The nuclear radiation protection concrete according to claim 1, characterized in that: The barite sand is medium sand with a fineness modulus of 2.3-2.5 and a barium sulfate content of ≥80%.

5. The nuclear radiation protection concrete according to claim 1, characterized in that: The silica fume is silicon powder with a specific surface area of ​​25-35m 2 / g.

6. The nuclear radiation protection concrete according to claim 1, characterized in that: The crushed stone is 2-10 mm granite crushed stone with an apparent density of 2300-2800 kg / m 3 .

7. The nuclear radiation protection concrete according to claim 1, characterized in that: The molecular weight of the polyethylene glycol is 2000-6000.

8. The method for preparing nuclear radiation protection concrete according to any one of claims 1 to 7, characterized in that: The specific steps include: Weigh the cement, the barite sand, and the crushed stone according to weight, and stir and mix them evenly to obtain a dry material; Add the radiation shielding agent and the silica fume to one-half of the amount of water, stir and mix evenly, and add to the dry material to obtain a premix; Weigh the retarder, the polycarboxylate water-reducing agent, the defoamer, the thickener, and the admixture in parts by weight, and add them to the remaining water to form a liquid material; The liquid material is added to the premix and stirred evenly to obtain the nuclear radiation protection concrete.

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