CN108484057B - Large-volume anti-cracking radiation-proof concrete based on waste glass and preparation method thereof - Google Patents
Large-volume anti-cracking radiation-proof concrete based on waste glass and preparation method thereof Download PDFInfo
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- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B28/00—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
- C04B28/02—Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements containing hydraulic cements other than calcium sulfates
- C04B28/04—Portland cements
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- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00241—Physical properties of the materials not provided for elsewhere in C04B2111/00
- C04B2111/00258—Electromagnetic wave absorbing or shielding materials
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- C04B2201/20—Mortars, concrete or artificial stone characterised by specific physical values for the density
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- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2201/00—Mortars, concrete or artificial stone characterised by specific physical values
- C04B2201/50—Mortars, concrete or artificial stone characterised by specific physical values for the mechanical strength
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Abstract
The invention discloses a large-volume reactor based on waste glassThe radiation-proof concrete comprises the following components in percentage by weight: 140 kg/m of water3(ii) a Cement 100-300kg/m3(ii) a 30-100kg/m of glass powder3(ii) a 50-180kg/m of fly ash3(ii) a 800-class fine aggregate 1100kg/m3(ii) a 1400-kg/m coarse aggregate3(ii) a 0.35-1.9kg/m of composite modifier3(ii) a 2.1-7.8kg/m of water reducing agent30.6-1.2kg/m of fiber3(ii) a Wherein the coarse aggregate is formed by mixing barite and lead glass, and the fine aggregate is formed by mixing borosilicate glass sand and barite sand. The obtained large-volume anti-cracking radiation-proof concrete has excellent working performance, mechanical property, anti-cracking performance, durability and shielding effect; and can efficiently utilize the waste glass containing lead, boron and the like as resources, and has remarkable economic and environmental benefits.
Description
Technical Field
The invention belongs to the field of constructional engineering, and particularly relates to a large-volume anti-cracking radiation-proof concrete based on waste glass and a preparation method thereof.
Background
The waste glass is an important component of the urban solid garbage, and the waste glass accounts for about 6-11% of the total amount of the solid garbage in China. Industrial waste glass can be used for the reproduction of glass, but daily waste glass is mostly disposed in a landfill mode because the quality of products is affected when the glass is reproduced. The proportion of the lead-containing oxide in the CRT glass exceeds 20%. Landfill of lead-containing substances causes pollution to soil and water sources. The waste glass of heat-resistant cookers, electric vacuum glass and optical glass is borosilicate glass, and the utilization of high added value is urgently needed. However, the waste glass is chemically stable and cannot be decomposed by microorganisms, and the landfill treatment mode not only pollutes the environment but also occupies a large amount of land resources.
In addition, in the design of radiation-proof large-volume concrete, on one hand, the apparent density of the concrete needs to be improved, on the other hand, a neutron absorber needs to be doped, the compactness of the concrete is improved, an anti-cracking design is carried out, and the radiation-proof function of the concrete is improved. The natural ore with larger apparent density such as barite is only selected to be used as the coarse and fine aggregate of the concrete, the potential risk of crack occurrence exists for the concrete with overlarge volume and the requirement of temperature rise control, and the problem of poor effect of shielding gamma rays exists at the same time. Therefore, the further research on the large-volume radiation-proof concrete with the advantages of low heat and shrinkage, good homogeneity, excellent durability, excellent shielding performance and the like has important research and application significance.
The recycling of domestic waste glass starts late, the utilization of the waste glass can be greatly promoted by developing a new way for recycling the high added value of the waste glass, good environmental benefit, social benefit and economic benefit are obtained, and low-carbon production is realized. Meanwhile, the radiation-proof large-volume anti-cracking concrete needs high-quality shielding aggregate and admixture to realize excellent performances of low heat, low shrinkage, radiation protection, crack resistance and high durability.
Disclosure of Invention
The invention aims to provide a large-volume anti-cracking radiation-proof concrete based on waste glass, aiming at the defects in the prior art, which can realize the high-efficiency utilization of various waste glass and can show the advantages of low heat and shrinkage, good homogeneity, excellent durability, excellent shielding performance and the like.
In order to achieve the purpose, the invention adopts the technical scheme that:
the mass anti-cracking radiation-proof concrete based on the waste glass comprises water, a cementing material, fine aggregates, coarse aggregates, a composite modifier, a water reducer and fibers, wherein the cementing material comprises cement and mineral admixtures, the coarse aggregates comprise barite and lead glass, the fine aggregates comprise borosilicate glass sand and barite sand, and the mineral admixtures comprise glass powder and fly ash; 140 kg/m of water3(ii) a Cement 100-300kg/m3(ii) a 30-100kg/m of glass powder3(ii) a 50-180kg/m of fly ash3(ii) a 800-class fine aggregate 1100kg/m3(ii) a 1400-kg/m coarse aggregate3(ii) a Composite material0.35-1.9kg/m of sex agent3(ii) a 2.1-7.8kg/m of water reducing agent30.6-1.2kg/m of fiber3。
The fineness modulus of the fine aggregate is 2.3-3.2, the mass ratio of borosilicate glass sand to barite sand in the fine aggregate is 1 (1.0-5.0), and the apparent density of the barite sand is 3800-4200 kg/m3And the barite powder content is less than 8 wt%. The borosilicate glass sand is prepared from optical glass waste, and the boron content of the borosilicate glass sand is more than 10 wt%.
The mass ratio of barite to lead glass aggregate in the coarse aggregate is 1 (1.0-3.0), and the coarse aggregate is 5-31.5 m continuous gradation; wherein the apparent density of the barite is 3900-4400 kg/m3The barium sulfate content is more than 85 wt%; lead glass aggregate is made of CRT glass waste and has apparent density of more than 2800kg/m3The lead content is more than 20 wt%.
Preferably, the mass ratio of the glass powder to the fly ash is 1 (1.0-4.0); the glass powder and the fly ash form a mineral admixture.
In the scheme, the particle size of the glass powder is less than 30 mu m; SiO in glass powder2Is greater than 70 wt%.
In the above scheme, the cement is low-heat portland cement or ordinary portland cement.
In the scheme, the water reducing agent is a polycarboxylic acid high-efficiency water reducing agent.
In the scheme, the fibers can be polypropylene fibers, the diameter is less than or equal to 30 microns, the length is less than or equal to 50mm, and the breaking strength is more than or equal to 200 MPa.
In the scheme, the composite modifier is prepared by mixing methyl cellulose ether, lithium carbonate, gypsum and hydrated lime according to the mass ratio of 1 (0.5-0.8) to (2-5) (mixing for 3-5 min by using a dry powder mixer and the like).
The preparation method of the large-volume anti-cracking radiation-proof concrete comprises the following steps:
1) weighing the raw materials in proportion, wherein the components and the content thereof comprise: 140 kg/m of water3(ii) a Cement 100-300kg/m3(ii) a 30-100kg/m of glass powder3(ii) a 50-180kg/m of fly ash3(ii) a Fine aggregate 800-m3(ii) a 1400-kg/m coarse aggregate3(ii) a 0.35-1.9kg/m of composite modifier3(ii) a 2.1-7.8kg/m of water reducing agent30.6-1.2kg/m of fiber3；
2) Uniformly mixing the weighed cement, glass powder, fly ash, fine aggregate, coarse aggregate, composite modifier and fiber to obtain a premixed material;
3) adding a water reducing agent, fibers and water into the premixed material obtained in the step 4) according to the proportion, and stirring for more than 120s until the materials are fully and uniformly mixed to obtain the large-volume anti-cracking radiation-proof concrete based on the waste glass.
The principle of the invention is as follows:
1) aiming at the cracking problem of large-volume radiation-proof concrete, the glass powder and the fly ash are adopted in large mixing amount, the early activity of the glass powder is low, the cementing material with low temperature rise can be prepared, meanwhile, the small glass powder can be uniformly dispersed in pores of the cementing material, C-S-H gel generated by volcanic ash reaction fills the pores, the migration difficulty of water in the concrete under a dry condition is increased, the compactness of the concrete is improved, the shrinkage rate of the concrete is reduced, and the dry shrinkage is compensated correspondingly; along with the increase of the mixing amount of the waste glass powder, the rate of filling pores by C-S-H gel generated by volcanic ash reaction is increased, the difficulty of water movement is increased, and the shrinkage rate of concrete is reduced; by adopting a closest packing design method, the compactness and the homogeneity of the concrete can be effectively improved, the problems of hydration temperature rise and self-shrinkage of the concrete are reduced, the polypropylene fiber components are added, the effects of crack resistance, toughening, wear resistance and permeability resistance are exerted, the crack resistance and the radiation resistance of the concrete are realized, and the high added value of glass wastes is utilized;
2) aiming at the problem that heavy aggregate is easy to separate into layers and segregate in large-volume radiation-proof concrete due to settlement of the heavy aggregate, the mixing proportion and the grading requirement of the heavy spar and the lead glass aggregate are optimized by adopting the principles of proportion optimization combination, aggregate interference and the like, so that the light and heavy aggregates collide in cement paste to form an effective aggregate interference effect, the sinking rate of the heavy spar is inhibited, the layering is reduced, and the homogeneity of the concrete is increased; meanwhile, the powder composition in the cementing material is optimized, the fly ash and the glass powder are introduced as admixtures, and the cellulose ether is added, so that the viscosity of the concrete is increased in a certain range to form gel, the viscosity of the cement paste is improved, a micro-crosslinking structure is introduced to form gel, and the cohesiveness of the paste is improved;
3) aiming at the problems of alkali-aggregate reaction and poor durability of the large-volume radiation-proof concrete caused by glass aggregate, the potential threat of the alkali-aggregate reaction in the concrete is reduced to the greatest extent by optimizing the design mixing proportion and adding high-content fly ash and a composite modifier; the early strength of the concrete is improved by activating active ingredients in a gelling system through alkali activation and sulfate activation, and the radiation protection performance and the durability of the concrete are further ensured;
4) the invention increases the shielding effect of the large-volume radiation-proof concrete, utilizes the thickness of the large-volume concrete and the compactness of the concrete to increase the shielding effect, and simultaneously introduces high-density barite, lead glass containing Pb and borosilicate glass containing B, thereby effectively shielding X rays, gamma rays and neutron flow and enhancing the comprehensive radiation-proof function of the concrete.
Compared with the prior art, the invention has the beneficial effects that:
1) the bulk anti-cracking radiation-proof concrete based on the waste glass provided by the invention has excellent working performance, mechanical property, anti-cracking performance, durability and shielding effect.
2) The waste glass is reasonably used as concrete coarse and fine aggregates and admixtures, a proper process flow is provided, the lead-containing waste glass is efficiently recycled, and the method has obvious economic and environmental benefits.
Drawings
FIG. 1 is a flow chart of preparation of bulk crack-resistant radiation-proof concrete based on waste glass.
Detailed Description
In order to better understand the present invention, the following examples are further provided to illustrate the present invention, but the present invention is not limited to the following examples.
In the following examples, the preparation method of the lead glass aggregate, borosilicate glass sand and glass powder comprises the following steps: the waste glass enters a manual sorting and impurity removing process, CRT glass, optical glass and common glass in the waste glass are sorted and then are respectively conveyed into a hopper of a distributing device, metal impurities in the waste glass are removed by an iron removing device in the distributing device, cone glass and neck glass in the sorted CRT glass are finely broken and screened, the waste glass is distributed on respective conveying devices, the broken glass materials are secondarily screened by a screening device, light impurities are screened and removed, then screening and grading are carried out, and 5-20mm aggregate is prepared, wherein fine powder obtained by screening the CRT glass and the optical glass is classified into common glass fine powder, other broken large glass and medium glass directly enter a breaking and grading process; the screen glass in the CRT glass can also be used as common glass; finely crushing the sorted optical glass, selecting, screening and grading, and grading glass frit at each level into glass fine aggregate of sand grading in the area II; respectively grinding the sorted common glass and the glass fine powder collected by other processes into glass micro powder with the particle size of less than or equal to 30 mu m;
the apparent density of the optical glass (borosilicate glass sand) recovered in the above step is 2760kg/m3The boron content is 12 wt%; the apparent density of the obtained CRT glass (lead glass aggregate) was 2870kg/m3Lead content 24 wt%; SiO in glass micropowder (glass powder)2The mass fraction of (B) is 85wt%
In the following examples, P.O 42.5.5 ordinary portland cement was used as the cement, and the density was 3.1 to 3.4g/cm3The density of the fly ash is 0.8-1.1 g/cm3(ii) a The length of the polypropylene fiber is 16-24 mm, the diameter is 40-50 um, and the breaking strength is 260 MPa; the water reducing agent is a polycarboxylic acid high-efficiency water reducing agent; apparent density of 4000kg/m of barite3The barium sulfate content is 90 wt%; the apparent density of the barite sand is 3900kg/m3And the barite powder content is less than 8 wt%.
Example 1
The components and the contents of the components of the large-volume anti-cracking radiation-proof concrete based on the waste glass are shown in the table 1; wherein the coarse aggregate consists of lead glass aggregate and barite according to the mass ratio of 1:2 and is 5-31.5 mm continuous gradation; the fine aggregate is composed of borosilicate glass sand and barite sand according to the mass ratio of 1:5, and the fineness modulus of the fine aggregate is 2.5-3.0; the mineral admixture is composed of glass powder and fly ash according to the mass ratio of 1:4, and the mass ratio of methyl cellulose ether, lithium carbonate, gypsum and hydrated lime in the composite modifier is 1:0.5:2: 2; the preparation method of the large-volume anti-cracking radiation-proof concrete comprises the following steps: mixing the weighed cement, glass powder, fly ash, fine aggregate, coarse aggregate, composite modifier and fiber for 45s, and uniformly mixing to obtain a premixed material; and then adding a water reducing agent, fibers and water into the obtained premixed material according to the proportion, and stirring for 150s until the materials are fully and uniformly mixed to obtain the large-volume anti-cracking radiation-proof concrete based on the waste glass.
Table 1 mixing ratio of each raw material in the bulky radiation-proof concrete described in example 1
Example 2
The components and the contents of the components of the large-volume anti-cracking radiation-proof concrete based on the waste glass are shown in the table 2; wherein the coarse aggregate consists of lead glass aggregate and barite according to the mass ratio of 1:3 and is 5-31.5 mm continuous gradation; the fine aggregate is composed of borosilicate glass sand and barite sand according to the mass ratio of 1:4, and the fineness modulus of the fine aggregate is 2.5-3.0; the mineral admixture is composed of glass powder and fly ash according to the mass ratio of 1:3, and the mass ratio of methyl cellulose ether, lithium carbonate, gypsum and hydrated lime in the composite modifier is 1:0.6:3: 2; the preparation method of the large-volume anti-cracking radiation-proof concrete comprises the following steps: mixing the weighed cement, glass powder, fly ash, fine aggregate, coarse aggregate, composite modifier and fiber for 45s, and uniformly mixing to obtain a premixed material; and then adding a water reducing agent, fibers and water into the obtained premixed material according to the proportion, and stirring for 150s until the materials are fully and uniformly mixed to obtain the large-volume anti-cracking radiation-proof concrete based on the waste glass.
Table 2 mixing ratio of each raw material in the bulky radiation-proof concrete described in example 2
Example 3
The components and the contents of the components of the large-volume anti-cracking radiation-proof concrete based on the waste glass are shown in a table 3; wherein the coarse aggregate consists of lead glass aggregate and barite according to the mass ratio of 1:3 and is 5-31.5 mm continuous gradation; the fine aggregate is composed of borosilicate glass sand and barite sand according to the mass ratio of 1:3, and the fineness modulus of the fine aggregate is 2.5-3.0; the mineral admixture is composed of glass powder and fly ash according to the mass ratio of 1:1, and the mass ratio of methyl cellulose ether, lithium carbonate, gypsum and hydrated lime in the composite modifier is 1:0.5:5: 5; the preparation method of the large-volume anti-cracking radiation-proof concrete comprises the following steps: mixing the weighed cement, glass powder, fly ash, fine aggregate, coarse aggregate, composite modifier and fiber for 60s, and uniformly mixing to obtain a premixed material; and then adding a water reducing agent, fibers and water into the obtained premixed material according to the proportion, and stirring for 150s until the materials are fully and uniformly mixed to obtain the large-volume anti-cracking radiation-proof concrete based on the waste glass.
Table 3 mixing ratio of each raw material in the bulky radiation-proof concrete described in example 3
Example 4
The components and the contents of the components of the large-volume anti-cracking radiation-proof concrete based on the waste glass are shown in the table 4; wherein the coarse aggregate consists of lead glass aggregate and barite according to the mass ratio of 1:2 and is 5-31.5 mm continuous gradation; the fine aggregate is composed of borosilicate glass sand and barite sand according to the mass ratio of 1:3, and the fineness modulus of the fine aggregate is 2.5-3.0; the mineral admixture is composed of glass powder and fly ash according to the mass ratio of 1:1, and the mass ratio of methyl cellulose ether, lithium carbonate, gypsum and hydrated lime in the composite modifier is 1:0.8:4: 5; the preparation method of the large-volume anti-cracking radiation-proof concrete comprises the following steps: mixing the weighed cement, glass powder, fly ash, fine aggregate, coarse aggregate, composite modifier and fiber for 45s, and uniformly mixing to obtain a premixed material; and then adding a water reducing agent, fibers and water into the obtained premixed material according to the proportion, and stirring for 150s until the materials are fully and uniformly mixed to obtain the large-volume anti-cracking radiation-proof concrete based on the waste glass.
Table 4 mixing ratio of each raw material in the bulky radiation-proof concrete described in example 4
Comparative example 1
The mixing proportion of the bulk anti-cracking radiation-proof concrete is approximately the same as that of the concrete in example 1, except that no composite modifier is added in the mixing proportion.
Comparative example 2
The mixing ratio of the large-volume anti-cracking radiation-proof concrete is approximately the same as that of the concrete in the embodiment 1, the difference is that the aggregate grading composition is changed in the mixing ratio, the mass ratio of borosilicate glass sand to barite sand is 1:6, and the mass ratio of lead glass aggregate to barite is 2:1 for coarse aggregate.
The working performance, the electrical performance, the mechanical performance, the shrinkage performance, the radiation resistance and the like of the large-volume radiation-proof and crack-resistant concrete obtained in the examples 1 to 4 are respectively tested, and the results are respectively shown in tables 4 and 5.
Table 4 examples 1-4 service performance test results of bulk radiation-resistant anti-cracking concrete
TABLE 5 examples 1-4 radiation protection Properties of radiation protection crack resistant concrete of bulk
The results show that the large-volume radiation-proof anti-cracking concrete prepared by the invention can show excellent working performance, mechanical property, durability and radiation-proof shielding effect, and has good application prospect.
Application example
The large-volume anti-cracking radiation-proof concrete based on the waste glass is applied to large-volume concrete construction simulating a certain ion hospital linear accelerator room, the wall thickness is 2.5m, the roof thickness is 1.7m, C30 large-volume concrete is adopted in design, wherein the coarse aggregate is composed of lead glass aggregate and barite according to the mass ratio of 1:2 and is 5-31.5 mm continuous gradation; the fine aggregate is composed of borosilicate glass sand and barite sand according to the mass ratio of 1:3, and the fineness modulus of the fine aggregate is 2.5-3.0; the mineral admixture is composed of glass powder and fly ash according to the mass ratio of 1:1, and the mass ratio of methyl cellulose ether, lithium carbonate, gypsum and hydrated lime in the composite modifier is 1:0.8:4: 5. The use of the compounding ratios is shown in table 6.
The maximum temperature rise in the bulk concrete and the maximum temperature difference between the inside and the outside are measured by a temperature patrol instrument and a temperature measuring line, the surface crack condition is detected by a crack observation instrument 28 days after the form is removed, and meanwhile, the prepared bulk concrete is subjected to sample self-test on site and is cured to a certain age period, and the test results of the performances of the compressive strength, the splitting tensile strength, the impermeability grade and the like are shown in the table 7.
TABLE 6 bulk anti-radiation anti-crack concrete mix proportion
TABLE 7 Mass radiation-protection crack-resistant concrete Performance test
The test result shows that: the concrete prepared from the waste glass has good compressive strength and splitting tensile strength, the anti-cracking performance of the concrete is improved, the maximum internal temperature rise is far lower than the standard of less than or equal to 50 ℃ required by the specification, the internal and external temperature difference is far lower than the standard of less than or equal to 25 ℃, cracks do not appear in the concrete, the technical problem of splitting of the concrete is solved, and meanwhile, the lead glass and borosilicate glass aggregate in the waste glass are utilized to realize the excellent radiation shielding function of the concrete.
It is apparent that the above embodiments are only examples for clearly illustrating and do not limit the embodiments. Other variations and modifications will be apparent to persons skilled in the art in light of the above description. And are neither required nor exhaustive of all embodiments. And obvious variations or modifications are therefore intended to be included within the scope of the invention as claimed.
Claims (9)
1. The large-volume anti-cracking radiation-proof concrete based on the waste glass is characterized by comprising the following components in percentage by weight: 140 kg/m of water3(ii) a Cement 100-300kg/m3(ii) a 30-100kg/m of glass powder3(ii) a 50-180kg/m of fly ash3(ii) a 800-class fine aggregate 1100kg/m3(ii) a 1400-kg/m coarse aggregate3(ii) a 0.35-1.9kg/m of composite modifier3(ii) a 2.1-7.8kg/m of water reducing agent30.6-1.2kg/m of fiber3(ii) a Wherein the coarse aggregate is formed by mixing barite and lead glass aggregate, and the fine aggregate is formed by mixing borosilicate glass sand and barite sand;
the composite modifier is prepared by mixing methyl cellulose ether, lithium carbonate, gypsum and hydrated lime according to the mass ratio of 1 (0.5-0.8) to (2-5);
the fineness modulus of the fine aggregate is 2.3-3.2, and the mass ratio of borosilicate glass sand to barite sand in the fine aggregate is 1 (1.0-5.0); the mass ratio of barite to lead glass aggregate in the coarse aggregate is 1 (1.0-3.0), and the coarse aggregate is 5-31.5 mm continuous gradation.
2. The large-volume anti-cracking radiation-proof concrete according to claim 1, wherein the apparent density of the barite sand is 3800-4200 kg/m3The barite powder content is less than 8 wt%; the borosilicate glass sand is prepared from optical glass waste, and the boron content of the borosilicate glass sand is more than 10 wt%.
3. The large-volume anti-cracking radiation-proof concrete according to claim 1, wherein the apparent density of the barite is 3900-4400 kg/m3The barium sulfate content is more than 85 wt%; lead glass aggregate is made of CRT glass waste and has apparent density of more than 2800kg/m3The lead content is more than 20 wt%.
4. The large-volume anti-cracking radiation-proof concrete according to claim 1, wherein the mass ratio of the glass powder to the fly ash is 1 (1.0-4.0).
5. The high-volume crack-resistant radiation-proof concrete according to claim 1, wherein the cement is low-heat portland cement or ordinary portland cement.
6. The large-volume anti-cracking radiation protection concrete according to claim 1, wherein the water reducing agent is a polycarboxylic acid high-efficiency water reducing agent.
7. The large-volume anti-cracking radiation-proof concrete according to claim 1, wherein the fibers are polypropylene fibers, the diameter is less than or equal to 30 μm, the length is less than or equal to 50mm, and the breaking strength is greater than or equal to 200 MPa.
8. The high-volume crack-resistant radiation-proof concrete according to claim 1, wherein the particle size of the glass powder is below 30 μm; SiO in glass powder2Is greater than 70 wt%.
9. The preparation method of the large-volume anti-cracking radiation protection concrete as claimed in any one of claims 1 to 8, characterized by comprising the following steps:
1) weighing the raw materials in proportion, wherein the components and the content thereof comprise: 140 kg/m of water3(ii) a Cement 100-300kg/m3(ii) a 30-100kg/m of glass powder3(ii) a 50-180kg/m of fly ash3(ii) a 800-class fine aggregate 1100kg/m3(ii) a 1400-kg/m coarse aggregate3(ii) a Compound medicine0.35-1.9kg/m of synthetic modifier3(ii) a 2.1-7.8kg/m of water reducing agent30.6-1.2kg/m of fiber3；
2) Uniformly mixing the weighed cement, glass powder, fly ash, fine aggregate, coarse aggregate, composite modifier and fiber to obtain a premixed material;
3) adding a water reducing agent, fibers and water into the premixed material obtained in the step 2) according to the proportion, and stirring for more than 120s until the materials are fully and uniformly mixed to obtain the large-volume anti-cracking radiation-proof concrete based on the waste glass.
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| CN113045269B (en) * | 2021-03-15 | 2021-11-16 | 湖南工程学院 | Physical-chemical combined activated glass solid waste concrete and preparation method thereof |
| CN113683328B (en) * | 2021-09-08 | 2022-06-03 | 河南科技大学 | Radiation-proof heavy aggregate prepared from wastes and preparation method thereof |
| CN114804770B (en) * | 2022-05-06 | 2023-04-25 | 上海建工建材科技集团股份有限公司 | Iron ore anti-radiation concrete and preparation method thereof |
| CN115010437A (en) * | 2022-06-29 | 2022-09-06 | 中建商品混凝土有限公司 | Multi-density-grade pumping radiation-proof concrete |
| CN117800688B (en) * | 2024-03-01 | 2024-04-30 | 石家庄铁道大学 | High-temperature-resistant rubber concrete and preparation method thereof |
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| CN104529297A (en) * | 2014-12-18 | 2015-04-22 | 广东省建筑工程集团有限公司 | Neutron irradiation preventing low-hydration-heat barite concrete |
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| CN104529297A (en) * | 2014-12-18 | 2015-04-22 | 广东省建筑工程集团有限公司 | Neutron irradiation preventing low-hydration-heat barite concrete |
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| Title |
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| 废弃阴极射线管玻璃对重晶石混凝土性能的影响;石建军等;《建筑材料学报》;20160430;第19卷(第2期);第369-372、384页 * |
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