CN108059405B - Nuclear power station containment concrete - Google Patents
Nuclear power station containment concrete Download PDFInfo
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- CN108059405B CN108059405B CN201711276598.7A CN201711276598A CN108059405B CN 108059405 B CN108059405 B CN 108059405B CN 201711276598 A CN201711276598 A CN 201711276598A CN 108059405 B CN108059405 B CN 108059405B
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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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- 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
- C04B41/00—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
- C04B41/009—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone characterised by the material treated
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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
- C04B41/00—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
- C04B41/45—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements
- C04B41/50—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials
- C04B41/5007—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials with salts or salty compositions, e.g. for salt glazing
- C04B41/5014—Coating or impregnating, e.g. injection in masonry, partial coating of green or fired ceramics, organic coating compositions for adhering together two concrete elements with inorganic materials with salts or salty compositions, e.g. for salt glazing containing sulfur in the anion, e.g. sulfides
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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
- C04B41/00—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone
- C04B41/80—After-treatment of mortars, concrete, artificial stone or ceramics; Treatment of natural stone of only ceramics
- C04B41/81—Coating or impregnation
- C04B41/85—Coating or impregnation with inorganic materials
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
- G21C13/093—Concrete vessels
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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
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
- C04B2111/00862—Uses not provided for elsewhere in C04B2111/00 for nuclear applications, e.g. ray-absorbing concrete
-
- 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
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/20—Resistance against chemical, physical or biological attack
-
- 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
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/20—Resistance against chemical, physical or biological attack
- C04B2111/27—Water resistance, i.e. waterproof or water-repellent materials
-
- 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
- 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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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Abstract
The invention relates to a nuclear power station containment concrete which comprises, by mass, 52.5 or 42.5 parts of 130-broken cement, 60-120 parts of slag, 50-100 parts of metakaolin, 50-150 parts of boron glass sand, 800 parts of 600-broken nickel slag, 800 parts of 600-broken barite, 400 parts of 200-broken limonite, 300 parts of 100-broken ceramsite, 20-50 parts of lead fiber, 160 parts of 130-broken water, 4-6 parts of a water reducing agent and 4-6 parts of an early strength agent. And after the concrete is cured for 28 days, coating a layer of radiation protection coating on the inner surface of the concrete. The nuclear power station containment concrete prepared by the invention has good radiation resistance, can well shield alpha, beta, gamma rays and neutron rays, has good crack resistance, high temperature resistance and durability, and simultaneously utilizes solid wastes such as nickel slag, glass powder and the like, thereby solving the problems of resource waste and environmental pollution to a certain extent.
Description
Technical Field
The invention relates to the field of safety protection of nuclear power stations, in particular to nuclear power station containment concrete.
Background
A containment vessel, that is, a nuclear reactor containment vessel, is a building constituting the outermost periphery of a pressurized water reactor, and a primary function of a nuclear power plant containment vessel structure is to completely shield radioactive materials leaked from a reactor pressure vessel in a shell when a reactor is abnormally operated or out of control, which is the last barrier of nuclear power safety, so that the containment vessel must have extremely high structural safety and durability while having radiation protection capability. At present, the containment vessel of the nuclear power station mainly comprises a steel containment vessel, but has high manufacturing cost and poor fireproof performance, is not resistant to acid and alkali corrosion, mainly comprises brittle fracture when being damaged, and the concrete containment vessel replaces the steel containment vessel is a development trend. The existing concrete containment structure has low durability, and the poor fire resistance is an important factor for restricting the development of the concrete containment structure.
In addition, metallurgical slag (nickel slag and the like) generated by metallurgical enterprises is less applied in the building industry due to the stability problem, and most of the metallurgical slag is still treated in an open-air stacking and landfill mode, so that the environment is polluted, and resources are wasted. Glass production enterprises also face the problem of waste glass stacking.
Metakaolin has irregular molecular arrangement, is in a thermodynamic metastable state, has a large number of broken chemical bonds and has strong volcanic ash activity; the metakaolin has the advantages of low water requirement, similar reinforcing effect to silica fume, micro aggregate filling effect, capability of reducing the porosity of concrete, improvement of pore structure and improvement of the compactness of set cement, low price of one tenth of that of silica fume, and wide development prospect.
The boron-containing substance has the effect of weakening the penetrating strength of neutron flow, the boron glass sand is used as a carrier of boron element, and the boron-containing substance is added into the concrete in a fine aggregate mode, so that the boron content of the concrete can be improved, the boron glass sand does not react with other components of the concrete, and the radiation resistance of the concrete can be greatly improved.
The lead has the characteristics of high atomic number and high density, has important significance in the field of nuclear radiation protection, and can play a role in ray protection and effectively enhance the shock resistance of concrete by taking lead fibers as a lead element carrier. The barite, limonite and other ores also have larger atomic number and higher apparent density, and can effectively prevent rays from penetrating through concrete.
The ceramsite has the advantages of light weight and high strength, and the sintered ceramsite has excellent fire resistance, and can enhance the fire resistance of concrete when added into the concrete. And the ceramsite has light weight, low elastic modulus, good deformation resistance and good seismic resistance.
The invention utilizes metakaolin to prepare the concrete with compactness and extremely high durability, utilizes boron glass sand, barite, limonite, lead fiber and barium sulfate coating to greatly enhance the radiation-proof capability, adopts sintered ceramsite as aggregate to control the volume weight of the concrete, also enhances the fire resistance of the concrete, fully utilizes nickel slag, and avoids environmental pollution and resource waste.
Disclosure of Invention
The technical problem is as follows: the invention aims to solve the technical problem of providing the containment concrete for the nuclear power station, which firstly solves the defects of overlarge volume weight and weak impact resistance and high temperature resistance of common containment concrete and secondly solves the problem that solid waste resources such as nickel slag occupy land and pollute the environment.
The technical scheme is as follows: the nuclear power station containment concrete comprises, by mass, 52.5 or 42.5 parts of cement 130-containing materials, 60-120 parts of slag, 50-100 parts of metakaolin, 50-150 parts of boron glass sand, 800 parts of nickel slag 600-containing materials, 800 parts of barite 600-containing materials, 400 parts of limonite 200-containing materials, 300 parts of ceramsite 100-containing materials, 20-50 parts of lead fibers, 160 parts of water 130-containing materials, 4-6 parts of a water reducing agent and 4-6 parts of an early strength agent.
The metakaolin is prepared by processing kaolin at the high temperature of 800 ℃, and the activity index is 120%.
The particle size of the boron glass sand<2mm, SiO as the main component2、B2O3The boron content is 15%.
The particle size of the nickel slag is less than 5mm, and the nickel slag is water-quenched nickel slag.
The barite BaSO4The content is not less than 80 percent, and the bulk density is 3000-3100kg/m3The content of sulfide and sulfate compounds containing gypsum or pyrite is not more than 7%, and the particle size is 10-25 mm.
The limonite Fe2O3The content is more than or equal to 70 percent, and the content of impurities<0.5 percent and the grain diameter is 10-25 mm.
The ceramsite is light sintered ceramsite, and the bulk density of the ceramsite is less than or equal to 700kg/m3The grain diameter is 5-10 mm.
The lead fiber has a diameter of 30-60 μm and a length of 10-50 mm.
The early strength agent is an I-type triethanolamine organic early strength agent, and the mass fraction is more than or equal to 99.0%.
And after the concrete is cured for 28 days, coating a layer of radiation protection coating on the inner surface of the concrete. The radiation-proof coating is precipitated BaSO with polyimide or polyoxadiazole as a binder4And (3) organic solvent coating.
Has the advantages that: 1) the high-temperature resistance can be effectively improved by adopting the slag with large mixing amount; 2) metakaolin molecules are in a thermodynamic metastable state, a large number of broken chemical bonds exist, the metakaolin has strong pozzolanic activity, the water requirement of the metakaolin is less than that of silica fume, the concrete reinforcing effect is similar to that of the silica fume, the metakaolin has a micro aggregate filling effect, the concrete void ratio can be reduced, the pore structure is improved, the compactness of cement stone is improved, and the price is only one tenth of that of the silica fume; 3) the boron glass sand is used as a carrier of boron element, and is added into the concrete in a fine aggregate mode, so that the boron content of the concrete can be improved, and the boron glass sand does not react with other components of the concrete, and the radiation resistance of the concrete can be greatly enhanced; 4) the lead has the characteristics of high atomic number and high density, has important significance in the field of nuclear radiation protection, and can play a role in ray protection and effectively enhance the shock resistance of concrete by taking lead fiber as a lead element carrier; 5) the nickel slag is utilized in the concrete, so that solid waste resources are fully utilized, the environmental pollution is effectively avoided, and the resources are saved; 6) the sintered ceramsite is applied to the concrete, so that the fire resistance and the shock resistance of the concrete can be effectively enhanced, the durability of the concrete is improved, and the volume weight of the concrete can be effectively controlled due to the characteristics of light weight and high strength; 7) the inner surface of the concrete is coated with a layer of radiation-proof coating, so that X rays and gamma rays can be effectively shielded, the radiation leakage can be effectively prevented, and the radiation resistance of the concrete is enhanced.
Detailed Description
The invention relates to a nuclear power station containment concrete which is characterized by comprising, by mass, 52.5 or 42.5 parts of cement 130-containing materials 200 parts, 60-120 parts of slag, 50-100 parts of metakaolin, 50-150 parts of boron glass sand, 800 parts of nickel slag 600-containing materials, 800 parts of barite 600-containing materials, 400 parts of limonite 200-containing materials, 300 parts of ceramsite 100-containing materials, 20-50 parts of lead fibers, 160 parts of water 130-containing materials, 4-6 parts of a water reducing agent and 4-6 parts of an early strength agent. And after the concrete is cured for 28 days, coating a layer of radiation protection coating on the inner surface of the concrete.
The metakaolin is prepared by processing kaolin at the high temperature of 800 ℃, and the activity index is 120%.
The particle size of the boron glass sand<2mm, SiO as the main component2、B2O3The boron content is 15%.
The particle size of the nickel slag is less than 5mm, and the nickel slag is water-quenched nickel slag.
The barite BaSO4The content is not less than 80 percent, and the bulk density is 3000-3100kg/m3The content of gypsum or pyrite sulfide and sulfate compounds is not higher than that of gypsum or pyriteAnd when the particle size is over 7 percent, the particle size is 10-25 mm.
The limonite Fe2O3The content is more than or equal to 70 percent, and the content of impurities<0.5 percent and the grain diameter is 10-25 mm.
The ceramsite is light sintered ceramsite, and the bulk density of the ceramsite is less than or equal to 700kg/m3The grain diameter is 5-10 mm.
The lead fiber has a diameter of 30-60 μm and a length of 10-50 mm.
The early strength agent is an I-type triethanolamine organic early strength agent, and the mass fraction is more than or equal to 99.0%.
The radiation-proof coating is precipitated BaSO with polyimide or polyoxadiazole as a binder4And (3) organic solvent coating.
The first embodiment,
The nuclear power station containment concrete comprises the following components in parts by mass: 200 parts of PII 42.5 cement, 120 parts of slag, 50 parts of metakaolin, 100 parts of boron glass sand, 700 parts of nickel slag, 800 parts of barite, 200 parts of limonite, 200 parts of ceramsite, 40 parts of lead fiber, 160 parts of water, 4 parts of polycarboxylic acid water reducing agent and 5 parts of early strength agent. After the concrete is cured for 28 days, a layer of precipitated BaSO with polyimide as a binder is coated on the inner surface of the concrete4Organic solvent radiation-proof paint.
Example II,
The nuclear power station containment concrete comprises the following components in parts by mass: 140 parts of PII52.5 cement, 60 parts of slag, 100 parts of metakaolin, 50 parts of boron glass sand, 750 parts of nickel slag, 700 parts of barite, 400 parts of limonite, 100 parts of ceramsite, 50 parts of lead fiber, 130 parts of water, 6 parts of polycarboxylic acid water reducing agent and 4.5 parts of early strength agent. After the concrete is cured for 28 days, a layer of precipitated BaSO with polyoxadiazole as a binder is coated on the inner surface of the concrete4Organic solvent radiation-proof paint.
Example III,
The nuclear power station containment concrete comprises the following components in parts by mass: 130 parts of PII 42.5 cement, 100 parts of slag, 80 parts of metakaolin, 150 parts of boron glass sand, 600 parts of nickel slag, 600 parts of barite, 300 parts of limonite, 300 parts of ceramsite, 20 parts of lead fiber, 140 parts of water, 4.5 parts of polycarboxylic acid water reducing agent and 6 parts of early strength agent. After the concrete is cured for 28 days, the inner surface of the concrete is coveredCoating a layer of precipitated BaSO with polyoxadiazole as binder4Organic solvent radiation-proof paint.
Example four,
The nuclear power station containment concrete comprises the following components in parts by mass: 160 parts of PII52.5 cement, 80 parts of slag, 90 parts of metakaolin, 70 parts of boron glass sand, 800 parts of nickel slag, 700 parts of barite, 200 parts of limonite, 200 parts of ceramsite, 50 parts of lead fiber, 150 parts of water, 5 parts of polycarboxylic acid water reducing agent and 4 parts of early strength agent. After the concrete is cured for 28 days, a layer of precipitated BaSO with polyimide as a binder is coated on the inner surface of the concrete4Organic solvent radiation-proof paint.
The performance evaluation indexes of the concrete are executed according to a common concrete mixture performance test method (GB/T50080-2002), a common concrete mechanical test method (GB/T50081-2002) and a common concrete long-term performance and durability test method standard (GB/T50082-2009). And (3) drying the surface moisture of the concrete cured for 28 days, heating to 600 ℃, keeping the temperature for 2 hours, naturally cooling to room temperature, and then carrying out mechanical property test.
Specific performance index comparison ratios of the containment concrete prepared in examples 1 to 4 of the present invention and the ordinary containment concrete (i.e., comparative example) are shown in table 1.
The comparative concrete comprises the following components in parts by mass: 400 parts of PII52.5 cement, 800 parts of sand, 1200 parts of broken stone, 140 parts of water and 6 parts of polycarboxylic acid water reducing agent.
TABLE 1
The performance indexes of the concrete strength of the containment vessel, the residual proportion of the compressive strength after high temperature, the water penetration resistance grade, the compressive strength and corrosion resistance coefficient of the sulfate corrosion after 60 times of dry and wet cycles and the like are all superior to those of a comparison sample.
The invention 1) adopts the slag with large mixing amount, which can effectively increase the high temperature resistance; 2) metakaolin molecules are in a thermodynamic metastable state, a large number of broken chemical bonds exist, the metakaolin has strong pozzolanic activity, the water requirement of the metakaolin is less than that of silica fume, the concrete reinforcing effect is similar to that of the silica fume, the metakaolin has a micro aggregate filling effect, the concrete void ratio can be reduced, the pore structure is improved, the compactness of cement stone is improved, and the price is only one tenth of that of the silica fume; 3) the boron glass sand is used as a carrier of boron element, and is added into the concrete in a fine aggregate mode, so that the boron content of the concrete can be improved, and the boron glass sand does not react with other components of the concrete, and the radiation resistance of the concrete can be greatly enhanced; 4) the lead has the characteristics of high atomic number and high density, has important significance in the field of nuclear radiation protection, and can play a role in ray protection and effectively enhance the shock resistance of concrete by taking lead fiber as a lead element carrier; 5) the nickel slag is utilized in the concrete, so that solid waste resources are fully utilized, the environmental pollution is effectively avoided, and the resources are saved; 6) the sintered ceramsite is applied to the concrete, so that the fire resistance and the shock resistance of the concrete can be effectively enhanced, the durability of the concrete is improved, and the volume weight of the concrete can be effectively controlled due to the characteristics of light weight and high strength; 7) the inner surface of the concrete is coated with a layer of radiation-proof coating, so that X rays and gamma rays can be effectively shielded, the radiation leakage can be effectively prevented, and the radiation resistance of the concrete is enhanced.
The technical means disclosed in the invention scheme are not limited to the technical means disclosed in the above embodiments, but also include the technical scheme formed by any combination of the above technical features. It should be noted that those skilled in the art can make various improvements and modifications without departing from the principle of the present invention, and such improvements and modifications are also considered to be within the scope of the present invention.
Claims (7)
1. The nuclear power station containment concrete is characterized by comprising, by mass, 52.5 or 42.5 parts of cement 130 and 200 parts of cement,
60-120 parts of slag,
50-100 parts of metakaolin,
50-150 parts of boron glass sand,
600 portions and 800 portions of nickel slag,
600 portions of barite and 800 portions of barite,
200 portions of limonite and 400 portions of limonite,
100 portions of ceramsite and 300 portions of ceramsite,
20-50 parts of lead fiber, namely,
130 portions of water and 160 portions of water,
4-6 parts of a water reducing agent,
4-6 parts of an early strength agent,
the metakaolin is prepared by processing kaolin at the high temperature of 800 ℃, and the activity index is 120%;
the particle size of the boron glass sand<2mm, SiO as the main component2、B2O315% of boron-containing mass;
the particle size of the nickel slag is less than 5mm, and the nickel slag is water-quenched nickel slag.
2. The nuclear power plant containment concrete as recited in claim 1, wherein the barite BaSO4The content is not less than 80 percent, and the bulk density is 3000-3100kg/m3The content of sulfide and sulfate compounds containing gypsum or pyrite is not more than 7%, and the particle size is 10-25 mm.
3. The nuclear power plant containment concrete according to claim 1, wherein the limonite Fe2O3The content is more than or equal to 70 percent, and the content of impurities<0.5 percent and the grain diameter is 10-25 mm.
4. The nuclear power plant containment concrete as recited in claim 1, wherein the ceramsite is a lightweight sintered ceramsite with a bulk density of 700kg/m or less3The grain diameter is 5-10 mm.
5. The nuclear power plant containment concrete as recited in claim 1 wherein the lead fibers have a diameter of 30-60 μm and a length of 10-50 mm.
6. The nuclear power station containment concrete as recited in claim 1, wherein the early strength agent is a type I triethanolamine organic early strength agent, and the mass fraction is greater than or equal to 99.0%.
7. The nuclear power plant containment concrete as recited in claim 1, wherein the concreteCharacterized in that after the concrete is cured for 28 days, a layer of radiation-proof paint is coated on the inner surface of the concrete; the radiation-proof coating is precipitated BaSO with polyimide or polyoxadiazole as a binder4And (3) organic solvent coating.
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| CN112010593B (en) * | 2020-08-25 | 2022-03-29 | 湖州上建混凝土有限公司 | Radiation-proof concrete and preparation method thereof |
| CN113072341A (en) * | 2021-04-15 | 2021-07-06 | 杨荣飞 | Portland cement radiation-proof concrete and production process thereof |
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- 2017-12-06 CN CN201711276598.7A patent/CN108059405B/en active Active
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| CN101913828A (en) * | 2010-08-19 | 2010-12-15 | 武汉理工大学 | High anti-cracking large volume radiation-proof concrete and construction process thereof |
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