CN108059405A - A kind of nuclear power plant containment shell concrete - Google Patents
A kind of nuclear power plant containment shell concrete Download PDFInfo
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- CN108059405A CN108059405A CN201711276598.7A CN201711276598A CN108059405A CN 108059405 A CN108059405 A CN 108059405A CN 201711276598 A CN201711276598 A CN 201711276598A CN 108059405 A CN108059405 A CN 108059405A
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- C—CHEMISTRY; METALLURGY
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- 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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- 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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- 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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- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
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- 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
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- 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
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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
- C04B2111/20—Resistance against chemical, physical or biological attack
- C04B2111/27—Water resistance, i.e. waterproof or water-repellent materials
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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
- 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
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Abstract
本发明涉及一种核电站安全壳混凝土,所用混凝土由以下质量份组成,52.5或42.5水泥130‑200份,矿渣60‑120份,偏高岭土50‑100份,硼玻璃砂50‑150份,镍渣600‑800份,重晶石600‑800份,褐铁矿200‑400份,陶粒100‑300份,铅纤维20‑50份,水130‑160份,减水剂4‑6份,早强剂4‑6份。混凝土养护28天后,在混凝土内表面涂覆一层防辐射涂料。本发明制备的核电站安全壳混凝土具有良好的防辐射性,能够很好的屏蔽α、β、γ射线和中子射线,且该混凝土具有良好的抗裂性能、耐高温性能及耐久性,同时利用了镍渣、玻璃粉等固体废弃物,在一定程度上解决了资源浪费和环境污染问题。The invention relates to a nuclear power plant containment concrete, which is composed of the following parts by mass: 130-200 parts of 52.5 or 42.5 cement, 60-120 parts of slag, 50-100 parts of metakaolin, 50-150 parts of boron glass sand, and nickel slag 600‑800 parts, barite 600‑800 parts, limonite 200‑400 parts, ceramsite 100‑300 parts, lead fiber 20‑50 parts, water 130‑160 parts, water reducing agent 4‑6 parts, early 4-6 copies of strong agent. After the concrete has been cured for 28 days, a layer of anti-radiation paint is applied to the inner surface of the concrete. The nuclear power plant containment concrete prepared by the invention has good radiation protection, can well shield α, β, γ rays and neutron rays, and the concrete has good crack resistance, high temperature resistance and durability, and can be used at the same time Solid waste such as nickel slag and glass powder has been eliminated, and the problems of resource waste and environmental pollution have been solved to a certain extent.
Description
技术领域technical field
本发明涉及核电站安全防护领域,具体涉及一种核电站安全壳混凝土。The invention relates to the field of nuclear power plant safety protection, in particular to a nuclear power plant containment concrete.
背景技术Background technique
安全壳即核反应堆安全壳,是构成压水反应堆最外围的建筑物,核电站安全壳结构的主要功能是在反应堆异常运行乃至失控时,将从反应堆压力容器泄露的放射性物质完全屏蔽在壳体内,是核电安全的最后一道屏障,因此安全壳必须具备极高的结构安全性和耐久性同时兼顾防辐射能力。目前核电站安全壳以钢安全壳为主,但是造价较高,防火性能差,且不耐酸碱侵蚀,发生破坏时以脆性断裂为主,混凝土安全壳取代钢结构安全壳是发展趋势。现有的混凝土安全壳结构耐久性不高,耐火性能差是制约其发展的重要因素。The containment shell is the nuclear reactor containment shell, which is the outermost building of the pressurized water reactor. The main function of the containment shell structure of the nuclear power plant is to completely shield the radioactive material leaked from the reactor pressure vessel in the shell when the reactor is operating abnormally or even out of control. The last barrier of nuclear power safety, so the containment must have extremely high structural safety and durability while taking into account radiation protection capabilities. At present, the containment of nuclear power plants is mainly made of steel containment, but the cost is high, the fire performance is poor, and it is not resistant to acid and alkali corrosion. When damage occurs, brittle fracture is the main type. It is a development trend for concrete containment to replace steel structure containment. The existing concrete containment structure has low durability and poor fire resistance is an important factor restricting its development.
另外冶金企业产生的冶金渣(镍渣等)由于安定性问题,在建筑行业应用较少,大部分仍然以露天堆放和填埋方式处理,这一方面污染环境、另一方面浪费了资源。玻璃产生企业也面临废弃玻璃堆置问题。In addition, metallurgical slag (nickel slag, etc.) produced by metallurgical enterprises is rarely used in the construction industry due to stability problems, and most of them are still disposed of in open-air stacks and landfills, which pollutes the environment on the one hand and wastes resources on the other. Glass production enterprises also face the problem of waste glass stacking.
偏高岭土分子排列不规则,呈现热力学介稳状态,存在大量断裂的化学键,具有很强的火山灰活性;且偏高岭土需水量小于硅灰,而对于混凝土增强效果与硅灰相似,具有微集料填充效应,可降低混凝土空隙率,改善孔结构,提高水泥石密实度,价格仅为硅灰的十分之一,具有广阔的开发前景。The molecular arrangement of metakaolin is irregular, showing a thermodynamic metastable state, there are a large number of broken chemical bonds, and it has strong pozzolanic activity; and metakaolin requires less water than silica fume, and its effect on concrete reinforcement is similar to that of silica fume, with micro-aggregate filling Effect, can reduce concrete porosity, improve pore structure, increase cement stone compactness, the price is only one tenth of silica fume, and has broad development prospects.
含硼物质具有减弱中子流穿透强度的作用,硼玻璃砂作为硼元素的载体,以细骨料的方式加入混凝土中可使混凝土含硼量提高,且与混凝土其他成分不反应,能大大增强混凝土抗辐射能力。Boron-containing substances have the effect of weakening the penetration strength of neutron flow. As the carrier of boron element, boron glass sand can be added to concrete in the form of fine aggregate to increase the boron content of concrete, and it does not react with other components of concrete. Enhance the radiation resistance of concrete.
铅具有高原子数、高密度的特性,用于核辐射防护领域有重要意义,以铅纤维作为铅元素载体既能发挥其射线防护的作用,又能有效增强混凝土抗冲击能力。重晶石、褐铁矿等矿石也具有较大的原子序数以及较高的表观密度,能有效阻挡射线穿透混凝土。Lead has the characteristics of high atomic number and high density, which is of great significance in the field of nuclear radiation protection. Using lead fiber as the lead element carrier can not only play the role of radiation protection, but also effectively enhance the impact resistance of concrete. Ores such as barite and limonite also have a large atomic number and a high apparent density, which can effectively block rays from penetrating concrete.
陶粒具有轻质高强的优点,烧结陶粒具有优异的耐火性,加入到混凝土中可增强混凝土耐火性。且由于陶粒质量轻,弹性模量低,抗形变性能好,具有良好的抗震性能。Ceramsite has the advantages of light weight and high strength. Sintered ceramsite has excellent fire resistance, and adding it to concrete can enhance the fire resistance of concrete. And because the ceramsite is light in weight, low in elastic modulus, good in deformation resistance, and has good shock resistance.
本发明利用偏高岭土,制备得较为密实、耐久性极高的混凝土,利用硼玻璃砂、重晶石、褐铁矿、铅纤维、硫酸钡涂料,大大增强了防辐射能力,采用烧结陶粒作为骨料,控制了混凝土容重,也增强了混凝土耐火性,同时充分利用了镍渣,避免了污染环境和浪费资源。The invention utilizes metakaolin to prepare relatively dense and highly durable concrete, utilizes boron glass sand, barite, limonite, lead fiber, and barium sulfate coating to greatly enhance the radiation protection ability, and adopts sintered ceramsite as the Aggregate controls the bulk density of concrete and enhances the fire resistance of concrete. At the same time, nickel slag is fully utilized to avoid environmental pollution and waste of resources.
发明内容Contents of the invention
技术问题:本发明要解决的技术问题是提供一种核电站安全壳混凝土,该发明首先解决了普通安全壳混凝土容重过大、抗冲击及耐高温能力不强的弱点,其次解决了镍渣等固废资源占用土地污染环境的问题。Technical problem: The technical problem to be solved by the present invention is to provide a kind of containment concrete for nuclear power plants. This invention firstly solves the weaknesses of ordinary containment concrete, such as excessive bulk density, low impact resistance and high temperature resistance, and secondly solves the problems of nickel slag and other solids. Waste resources occupy land and pollute the environment.
技术方案:本发明的核电站安全壳混凝土由以下质量份组成,52.5或42.5水泥130-200份,矿渣60-120份,偏高岭土50-100份,硼玻璃砂50-150份,镍渣600-800份,重晶石600-800份,褐铁矿200-400份,陶粒100-300份,铅纤维20-50份,水130-160份,减水剂4-6份,早强剂4-6份。Technical solution: The nuclear power plant containment concrete of the present invention is composed of the following parts by mass, 130-200 parts of 52.5 or 42.5 cement, 60-120 parts of slag, 50-100 parts of metakaolin, 50-150 parts of boron glass sand, and 600-200 parts of nickel slag. 800 parts, barite 600-800 parts, limonite 200-400 parts, ceramsite 100-300 parts, lead fiber 20-50 parts, water 130-160 parts, water reducing agent 4-6 parts, early strength agent 4-6 servings.
所述偏高岭土为高岭土在800℃高温下处理而成,活性指数为120%。The metakaolin is processed from kaolin at a high temperature of 800° C., and its activity index is 120%.
所述硼玻璃砂粒径<2mm,主要成分为SiO2、B2O3,含硼量15%。The particle diameter of the boron glass sand is less than 2 mm, the main components are SiO 2 and B 2 O 3 , and the boron content is 15%.
所述镍渣粒径小于5mm,为水淬镍渣。The particle size of the nickel slag is less than 5mm, which is water-quenched nickel slag.
所述重晶石BaSO4含量不低于80%,堆积密度3000-3100kg/m3,含石膏或黄铁矿的硫化物及硫酸化合物不超过7%,粒径在10-25mm。The barite BaSO 4 content is not less than 80%, the bulk density is 3000-3100kg/ m3 , the sulfide and sulfuric acid compound of gypsum or pyrite is not more than 7%, and the particle size is 10-25mm.
所述褐铁矿Fe2O3含量≥70%,杂质含量<0.5%,粒径在10-25mm。The limonite Fe 2 O 3 content is more than 70%, the impurity content is less than 0.5%, and the particle size is 10-25mm.
所述陶粒为轻质烧结陶粒,堆积密度≤700kg/m3,粒径5-10mm。The ceramsite is light sintered ceramsite, with a bulk density of ≤700kg/m 3 and a particle size of 5-10mm.
所述铅纤维直径在30-60μm,长度在10-50mm之间。The lead fiber has a diameter of 30-60 μm and a length of 10-50 mm.
所述早强剂为I型三乙醇胺类有机早强剂,质量分数≥99.0%。The early strength agent is a type I triethanolamine organic early strength agent with a mass fraction ≥ 99.0%.
混凝土养护28天后,在混凝土内表面涂覆一层防辐射涂料。所述防辐射涂料是以聚酰亚胺或聚恶二唑为粘结剂的沉淀BaSO4有机溶剂涂料。After the concrete has been cured for 28 days, a layer of anti-radiation paint is applied to the inner surface of the concrete. The anti-radiation paint is a precipitated BaSO4 organic solvent paint with polyimide or polyoxadiazole as a binder.
有益效果:1)采用大掺量矿渣,能有效增加耐高温能力;2)偏高岭土分子呈现热力学介稳状态,存在大量断裂的化学键,具有很强的火山灰活性,且偏高岭土需水量小于硅灰,而对于混凝土增强效果与硅灰相似,具有微集料填充效应,可降低混凝土空隙率,改善孔结构,提高水泥石密实度,价格仅为硅灰的十分之一;3)硼玻璃砂作为硼元素的载体,以细骨料的方式加入混凝土中可使混凝土含硼量提高,且与混凝土其他成分不反应,能大大增强混凝土抗辐射能力;4)铅具有高原子数、高密度的特性,用于核辐射防护领域有重要意义,以铅纤维作为铅元素载体既能发挥其射线防护的作用,又能有效增强混凝土抗冲击能力;5)将镍渣利用到混凝土中,充分利用固废资源,有效避免了环境污染和节约了资源;6)将烧结陶粒应用到混凝土中能有效增强混凝土耐火性,抗震性,提高混凝土耐久性,且由于轻质高强的特点,能有效控制混凝土容重;7)将混凝土内表面涂覆一层防辐射涂料,能有效屏蔽X射线和γ射线,有效防止射线外泄,增强混凝土抗辐射能力。Beneficial effects: 1) The use of a large amount of slag can effectively increase the high temperature resistance; 2) Metakaolin molecules present a thermodynamic metastable state, there are a large number of broken chemical bonds, and have strong pozzolanic activity, and metakaolin requires less water than silica fume , while the concrete reinforcement effect is similar to that of silica fume, with micro-aggregate filling effect, which can reduce concrete void ratio, improve pore structure, and increase cement stone density, and the price is only one-tenth of silica fume; 3) boron glass sand As a carrier of boron element, adding fine aggregate to concrete can increase the boron content of concrete, and it does not react with other components of concrete, which can greatly enhance the anti-radiation ability of concrete; 4) lead has a high atomic number and high density. It is of great significance to be used in the field of nuclear radiation protection. Using lead fiber as the carrier of lead element can not only play the role of radiation protection, but also effectively enhance the impact resistance of concrete; Waste resources, effectively avoiding environmental pollution and saving resources; 6) Applying sintered ceramsite to concrete can effectively enhance the fire resistance and earthquake resistance of concrete, improve the durability of concrete, and due to the characteristics of light weight and high strength, it can effectively control the concrete Bulk density; 7) The inner surface of the concrete is coated with a layer of anti-radiation paint, which can effectively shield X-rays and gamma rays, effectively prevent radiation leakage, and enhance the anti-radiation ability of concrete.
具体实施方式Detailed ways
本发明涉及一种核电站安全壳混凝土,其特征在于所用混凝土由以下质量份组成,52.5或42.5水泥130-200份,矿渣60-120份,偏高岭土50-100份,硼玻璃砂50-150份,镍渣600-800份,重晶石600-800份,褐铁矿200-400份,陶粒100-300份,铅纤维20-50份,水130-160份,减水剂4-6份,早强剂4-6份。混凝土养护28天后,在混凝土内表面涂覆一层防辐射涂料。The invention relates to a nuclear power plant containment concrete, which is characterized in that the concrete used is composed of the following parts by mass: 130-200 parts of 52.5 or 42.5 cement, 60-120 parts of slag, 50-100 parts of metakaolin, and 50-150 parts of boron glass sand , 600-800 parts of nickel slag, 600-800 parts of barite, 200-400 parts of limonite, 100-300 parts of ceramsite, 20-50 parts of lead fiber, 130-160 parts of water, 4-6 parts of water reducer parts, 4-6 parts of early strength agent. After the concrete has been cured for 28 days, a layer of anti-radiation paint is applied to the inner surface of the concrete.
所述偏高岭土为高岭土在800℃高温下处理而成,活性指数为120%。The metakaolin is processed from kaolin at a high temperature of 800° C., and its activity index is 120%.
所述硼玻璃砂粒径<2mm,主要成分为SiO2、B2O3,含硼量15%。The particle diameter of the boron glass sand is less than 2 mm, the main components are SiO 2 and B 2 O 3 , and the boron content is 15%.
所述镍渣粒径小于5mm,为水淬镍渣。The particle size of the nickel slag is less than 5mm, which is water-quenched nickel slag.
所述重晶石BaSO4含量不低于80%,堆积密度3000-3100kg/m3,含石膏或黄铁矿的硫化物及硫酸化合物不超过7%,粒径在10-25mm。The barite BaSO 4 content is not less than 80%, the bulk density is 3000-3100kg/ m3 , the sulfide and sulfuric acid compound of gypsum or pyrite is not more than 7%, and the particle size is 10-25mm.
所述褐铁矿Fe2O3含量≥70%,杂质含量<0.5%,粒径在10-25mm。The limonite Fe 2 O 3 content is more than 70%, the impurity content is less than 0.5%, and the particle size is 10-25mm.
所述陶粒为轻质烧结陶粒,堆积密度≤700kg/m3,粒径5-10mm。The ceramsite is light sintered ceramsite, with a bulk density of ≤700kg/m 3 and a particle size of 5-10mm.
所述铅纤维直径在30-60μm,长度在10-50mm之间。The lead fiber has a diameter of 30-60 μm and a length of 10-50 mm.
所述早强剂为I型三乙醇胺类有机早强剂,质量分数≥99.0%。The early strength agent is a type I triethanolamine organic early strength agent with a mass fraction ≥ 99.0%.
所述防辐射涂料是以聚酰亚胺或聚恶二唑为粘结剂的沉淀BaSO4有机溶剂涂料。The anti-radiation paint is a precipitated BaSO4 organic solvent paint with polyimide or polyoxadiazole as a binder.
实施例一、Embodiment one,
核电站安全壳混凝土由以下质量份组成:PII 42.5水泥200份,矿渣120份,偏高岭土50份,硼玻璃砂100份,镍渣700份,重晶石800份,褐铁矿200份,陶粒200份,铅纤维40份,水160份,聚羧酸减水剂4份,早强剂5份。混凝土养护28天后,在混凝土内表面涂覆一层以聚酰亚胺为粘结剂的沉淀BaSO4有机溶剂防辐射涂料。The containment concrete of a nuclear power plant is composed of the following 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, and ceramsite 200 parts, 40 parts of lead fiber, 160 parts of water, 4 parts of polycarboxylate superplasticizer, 5 parts of early strength agent. After the concrete was cured for 28 days, a layer of precipitated BaSO 4 organic solvent radiation-proof coating with polyimide as the binder was coated on the inner surface of the concrete.
实施例二、Embodiment two,
核电站安全壳混凝土由以下质量份组成:PII 52.5水泥140份,矿渣60份,偏高岭土100份,硼玻璃砂50份,镍渣750份,重晶石700份,褐铁矿400份,陶粒100份,铅纤维50份,水130份,聚羧酸减水剂6份,早强剂4.5份。混凝土养护28天后,在混凝土内表面涂覆一层以聚恶二唑为粘结剂的沉淀BaSO4有机溶剂防辐射涂料。The containment concrete of a nuclear power plant is composed of the following parts by mass: 140 parts of PII 52.5 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, ceramsite 100 parts, 50 parts of lead fiber, 130 parts of water, 6 parts of polycarboxylate superplasticizer, 4.5 parts of early strength agent. After the concrete was cured for 28 days, a layer of precipitated BaSO 4 organic solvent anti-radiation coating with polyoxadiazole as the binder was coated on the inner surface of the concrete.
实施例三、Embodiment three,
核电站安全壳混凝土由以下质量份组成:PII 42.5水泥130份,矿渣100份,偏高岭土80份,硼玻璃砂150份,镍渣600份,重晶石600份,褐铁矿300份,陶粒300份,铅纤维20份,水140份,聚羧酸减水剂4.5份,早强剂6份。混凝土养护28天后,在混凝土内表面涂覆一层以聚恶二唑为粘结剂的沉淀BaSO4有机溶剂防辐射涂料。The containment concrete of a nuclear power plant is composed of the following 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, ceramsite 300 parts, 20 parts of lead fiber, 140 parts of water, 4.5 parts of polycarboxylate superplasticizer, 6 parts of early strength agent. After the concrete was cured for 28 days, a layer of precipitated BaSO 4 organic solvent anti-radiation coating with polyoxadiazole as the binder was coated on the inner surface of the concrete.
实施例四、Embodiment four,
核电站安全壳混凝土由以下质量份组成:PII 52.5水泥160份,矿渣80份,偏高岭土90份,硼玻璃砂70份,镍渣800份,重晶石700份,褐铁矿200份,陶粒200份,铅纤维50份,水150份,聚羧酸减水剂5份,早强剂4份。混凝土养护28天后,在混凝土内表面涂覆一层以聚酰亚胺为粘结剂的沉淀BaSO4有机溶剂防辐射涂料。Containment concrete for nuclear power plants consists of the following parts by mass: 160 parts of PII 52.5 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, and ceramsite 200 parts, 50 parts of lead fiber, 150 parts of water, 5 parts of polycarboxylate superplasticizer, 4 parts of early strength agent. After the concrete was cured for 28 days, a layer of precipitated BaSO 4 organic solvent radiation-proof coating with polyimide as the binder was coated on the inner surface of the concrete.
混凝土性能考核指标按照《普通混凝土拌合物性能试验方法》(GB/T50080-2002)、《普通混凝土力学试验方法》(GB/T 50081-2002)和《普通混凝土长期性能和耐久性能试验方法标准》(GB/T 50082-2009)执行。将养护28d的混凝土晾干表面水分后加热到600℃,恒温2h,自然冷却至室温后进行力学性能测试。Concrete performance assessment indicators are in accordance with "Test Methods for Performance of Ordinary Concrete Mixtures" (GB/T50080-2002), "Test Methods for Ordinary Concrete Mechanics" (GB/T 50081-2002) and "Standards for Test Methods for Long-term Performance and Durability of Ordinary Concrete" "(GB/T 50082-2009) implementation. The concrete cured for 28 days was dried from the surface moisture, heated to 600°C, kept at a constant temperature for 2 hours, and then naturally cooled to room temperature for mechanical performance testing.
本发明实施例1-4制得的安全壳混凝土与普通安全壳混凝土(即对比例)具体性能指标对比如表1所示。Table 1 shows the comparison of specific performance indicators between the containment concrete prepared in Examples 1-4 of the present invention and ordinary containment concrete (ie, the comparative example).
而对比例混凝土由以下组份质量份组成:PII52.5水泥400份,砂800份,碎石1200份,水140份,聚羧酸减水剂6份。The comparative example concrete is composed of the following components by mass: 400 parts of PII52.5 cement, 800 parts of sand, 1200 parts of gravel, 140 parts of water, and 6 parts of polycarboxylate superplasticizer.
表1Table 1
本发明制备的安全壳混凝土强度、高温后抗压强度剩余比例、抗水渗等级、60次干湿循环硫酸盐侵蚀抗压强度耐蚀系数等性能指标均优于对比样。The strength of the containment concrete prepared by the invention, the remaining ratio of compressive strength after high temperature, the grade of water seepage resistance, the compressive strength and corrosion resistance coefficient of sulfate erosion after 60 dry-wet cycles are all better than those of the comparison sample.
本发明1)采用大掺量矿渣,能有效增加耐高温能力;2)偏高岭土分子呈现热力学介稳状态,存在大量断裂的化学键,具有很强的火山灰活性,且偏高岭土需水量小于硅灰,而对于混凝土增强效果与硅灰相似,具有微集料填充效应,可降低混凝土空隙率,改善孔结构,提高水泥石密实度,价格仅为硅灰的十分之一;3)硼玻璃砂作为硼元素的载体,以细骨料的方式加入混凝土中可使混凝土含硼量提高,且与混凝土其他成分不反应,能大大增强混凝土抗辐射能力;4)铅具有高原子数、高密度的特性,用于核辐射防护领域有重要意义,以铅纤维作为铅元素载体既能发挥其射线防护的作用,又能有效增强混凝土抗冲击能力;5)将镍渣利用到混凝土中,充分利用固废资源,有效避免了环境污染和节约了资源;6)将烧结陶粒应用到混凝土中能有效增强混凝土耐火性,抗震性,提高混凝土耐久性,且由于轻质高强的特点,能有效控制混凝土容重;7)将混凝土内表面涂覆一层防辐射涂料,能有效屏蔽X射线和γ射线,有效防止射线外泄,增强混凝土抗辐射能力。The present invention 1) adopts a large amount of slag, which can effectively increase the high temperature resistance; 2) metakaolin molecules present a thermodynamic metastable state, there are a large number of broken chemical bonds, and have strong pozzolanic activity, and metakaolin requires less water than silica fume, For concrete, the reinforcement effect is similar to that of silica fume, and it has a micro-aggregate filling effect, which can reduce the void ratio of concrete, improve the pore structure, and increase the compactness of cement stones, and the price is only one tenth of silica fume; 3) boron glass sand as The carrier of boron element can be added to concrete in the form of fine aggregate to increase the boron content of concrete, and it does not react with other components of concrete, which can greatly enhance the anti-radiation ability of concrete; 4) lead has the characteristics of high atomic number and high density It is of great significance to be used in the field of nuclear radiation protection. Using lead fiber as the lead element carrier can not only play the role of radiation protection, but also effectively enhance the impact resistance of concrete; 5) Utilize nickel slag in concrete and make full use of solid waste resources, effectively avoiding environmental pollution and saving resources; 6) Applying sintered ceramsite to concrete can effectively enhance the fire resistance and earthquake resistance of concrete, improve the durability of concrete, and due to the characteristics of light weight and high strength, it can effectively control the concrete density ; 7) The inner surface of the concrete is coated with a layer of anti-radiation paint, which can effectively shield X-rays and γ-rays, effectively prevent radiation leakage, and enhance the anti-radiation ability of concrete.
本发明方案所公开的技术手段不仅限于上述实施方式所公开的技术手段,还包括由以上技术特征任意组合所组成的技术方案。应当指出,对于本技术领域的普通技术人员来说,在不脱离本发明原理的前提下,还可以做出若干改进和润饰,这些改进和润饰也视为本发明的保护范围。The technical means disclosed in the solutions of the present invention are not limited to the technical means disclosed in the above embodiments, but also include technical solutions composed of any combination of the above technical features. It should be pointed out that for those skilled in the art, some improvements and modifications can be made without departing from the principle of the present invention, and these improvements and modifications are also regarded as the protection scope of the present invention.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112010593A (en) * | 2020-08-25 | 2020-12-01 | 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 |
| CN117342840A (en) * | 2023-09-27 | 2024-01-05 | 北京当代创新建设工程有限责任公司 | Nuclear radiation protection concrete and preparation method thereof |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101913828A (en) * | 2010-08-19 | 2010-12-15 | 武汉理工大学 | A high-crack-resistant large-volume radiation-proof concrete and its construction technology |
| CN102219459A (en) * | 2011-04-02 | 2011-10-19 | 武汉理工大学 | Radiation shield concrete and preparation method thereof |
| CN104478311A (en) * | 2014-11-24 | 2015-04-01 | 柳州立洁科技有限公司 | Anti-radiation insulating building block |
| CN105272027A (en) * | 2015-09-23 | 2016-01-27 | 江苏苏博特新材料股份有限公司 | Ultra-high performance concrete with compressive strength of 300MPa or more and preparation method |
| CN106977145A (en) * | 2017-04-13 | 2017-07-25 | 天津金隅混凝土有限公司 | A kind of radiation shield concrete |
| CN107434388A (en) * | 2017-07-24 | 2017-12-05 | 中国建筑材料科学研究总院 | A kind of spent fuel dry-type storage container concrete and preparation method thereof |
-
2017
- 2017-12-06 CN CN201711276598.7A patent/CN108059405B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101913828A (en) * | 2010-08-19 | 2010-12-15 | 武汉理工大学 | A high-crack-resistant large-volume radiation-proof concrete and its construction technology |
| CN102219459A (en) * | 2011-04-02 | 2011-10-19 | 武汉理工大学 | Radiation shield concrete and preparation method thereof |
| CN104478311A (en) * | 2014-11-24 | 2015-04-01 | 柳州立洁科技有限公司 | Anti-radiation insulating building block |
| CN105272027A (en) * | 2015-09-23 | 2016-01-27 | 江苏苏博特新材料股份有限公司 | Ultra-high performance concrete with compressive strength of 300MPa or more and preparation method |
| CN106977145A (en) * | 2017-04-13 | 2017-07-25 | 天津金隅混凝土有限公司 | A kind of radiation shield concrete |
| CN107434388A (en) * | 2017-07-24 | 2017-12-05 | 中国建筑材料科学研究总院 | A kind of spent fuel dry-type storage container concrete and preparation method thereof |
Non-Patent Citations (5)
| Title |
|---|
| 李凯琦等: "《风化型高岭土深加工技术》", 30 June 2017, 中国建材工业出版社 * |
| 柴立元等: "《冶金环保手册》", 30 April 2016, 中南大学出版社 * |
| 河海大学《水利大辞典》编辑修订委员会: "《水利大辞典》", 31 October 2015, 上海辞书出版社 * |
| 胡仁山等: "《混凝土工班组长手册》", 31 January 1996, 中国建筑工业出版社 * |
| 马一平等: "《建筑功能材料》", 31 March 2014, 同济大学出版社 * |
Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112010593A (en) * | 2020-08-25 | 2020-12-01 | 湖州上建混凝土有限公司 | Radiation-proof concrete and preparation method thereof |
| 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 |
| CN117342840A (en) * | 2023-09-27 | 2024-01-05 | 北京当代创新建设工程有限责任公司 | Nuclear radiation protection concrete and preparation method thereof |
| CN117342840B (en) * | 2023-09-27 | 2025-08-22 | 北京当代创新建设工程有限责任公司 | Nuclear radiation protection concrete and preparation method thereof |
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