CN102219459A - Radiation shield concrete and preparation method thereof - Google Patents
Radiation shield concrete and preparation method thereof Download PDFInfo
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- CN102219459A CN102219459A CN2011100839944A CN201110083994A CN102219459A CN 102219459 A CN102219459 A CN 102219459A CN 2011100839944 A CN2011100839944 A CN 2011100839944A CN 201110083994 A CN201110083994 A CN 201110083994A CN 102219459 A CN102219459 A CN 102219459A
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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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- 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
- Y02W—CLIMATE CHANGE MITIGATION TECHNOLOGIES RELATED TO WASTEWATER TREATMENT OR WASTE MANAGEMENT
- Y02W30/00—Technologies for solid waste management
- Y02W30/50—Reuse, recycling or recovery technologies
- Y02W30/91—Use of waste materials as fillers for mortars or concrete
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Abstract
本发明涉及一种防辐射混凝土及其制备方法。一种防辐射混凝土，其特征在于：包括胶结材料、粗骨料、细骨料、钢纤维、高效减水剂和水，所述胶结材料由普通硅酸盐水泥和无机矿物掺合料组成，所述无机矿物掺合料为硅灰和粉煤灰；所述细骨料为天然砂、硼玻璃粉和钢渣粉；所述粗骨料为钢段或钢段和钢渣的混合物，各组分的配比为：胶结材料500kg/m3，粗骨料1400～2215kg/m3，细骨料750～950kg/m3，水155～200kg/m3，高效减水剂按重量计为胶结材料总重量的0.5～1.0%，钢纤维按体积计为混凝土总体积的1.0～1.5%。该防辐射混凝土具有良好的力学性能和耐久性能，对γ射线具有良好的屏蔽效果，且屏蔽中子射线效果好；可综合回收利用废物，成本低廉。The invention relates to a radiation-proof concrete and a preparation method thereof. A kind of anti-radiation concrete is characterized in that: comprises cementing material, coarse aggregate, fine aggregate, steel fiber, superplasticizer and water, and described cementing material is made up of ordinary Portland cement and inorganic mineral admixture, The inorganic mineral admixture is silica fume and fly ash; the fine aggregate is natural sand, boron glass powder and steel slag powder; the coarse aggregate is a steel section or a mixture of steel section and steel slag, each component The ratio is: cementing material 500kg/m 3 , coarse aggregate 1400-2215kg/m 3 , fine aggregate 750-950kg/m 3 , water 155-200kg/m 3 , superplasticizer is the cementing material by weight 0.5-1.0% of the total weight, steel fiber by volume is 1.0-1.5% of the total volume of concrete. The anti-radiation concrete has good mechanical properties and durability, has a good shielding effect on gamma rays, and has a good shielding effect on neutron rays; it can comprehensively recycle waste and has low cost.
Description
Technical field:
The invention belongs to building material field, be specifically related to a kind of radiation shield concrete and preparation method thereof.
Background technology:
Nuclear technique has just been developed since being born rapidly, is obtaining application widely as various fields such as nuclear power, military affairs, education, scientific research, medical treatment, yet its security is its key that further develops of puzzlement always.As everyone knows, a large amount of rays that nuclear reaction produces can bring out the genovariation of multiple human incurable disease such as cancer, leukemia and multiple marrow cancer, big chest malignant tumour, infertility, miscarriage and fertility defective and inducing plant, the growth that harms the crops.
Radiation shield concrete is called radiation-shielding concrete, nuclear power concrete protection, shielding concrete, nuclear reactor concrete or loaded concrete again.It is as atomic reactor, particle accelerator and contain the protective material of radioactive source device, can effectively shield nuclear radiation, and described nuclear radiation refers generally to ray and neutron radiations such as α, β, γ, X.Wherein, a little less than α, the β ray penetration power, be absorbed easily, the protective material of general thickness just can block α, β ray.What therefore, antiradiation material mainly shielded is γ, x ray and neutron current.
The radiation shield concrete technology mainly is divided into two aspects both at home and abroad at present:
1) adopts magnetic iron ore, limonite ore or barite to gather materials, introduce the crystal water of quantity sufficient and the compound and the Additive thereof of light elements such as boracic, lithium simultaneously as thickness.This method is at present the most widely used a kind of, and wherein the thickness that density is high is gathered materials and can be shielded gamma-rays, and the compound that contains light element can effectively be caught neutron and do not formed the secondary gamma-rays, and the ray shield effect is better.But because it adopts the big material of density to do and gathers materials, concrete is easily emanated, and workability is poor, and hydration heat of cement is big, thereby causes concrete easy to crack, poor durability, and the curing safe effect of nuke rubbish is poor.
2) use technology of high performance concrete,, reduce concrete water-cement ratio, reduce the concrete shrinkage rate, improve concrete density and concrete cracking resistance ability by Adding Mineral Admixtures.Xi Wakesi nuclear power plant reactor inside and outside shell concrete as France is exactly this technology that adopts.But because this method does not adopt the big radioprotective of density to gather materials, thereby must just can reach the purpose that shields ray, and the ability of this concrete protection neutron ray is relatively poor by increasing concrete thickness.
Patent No. CN101805156A discloses a kind of method that adopts slag sand and barite to prepare radiation shield concrete as coarse aggregate, but the coarse aggregate that the radiation shield concrete of this method preparation adopts is slag and barite, because of different local slag chemical ingredientss inconsistent, thereby influence concrete weather resistance.And because barite fragility is big, mechanical stirring can cause its be broken into Powdered, thereby in practice of construction in order to reduce pulverizing, can only strictly control churning time, and it is inhomogeneous to cause concrete to stir, and the barite scarcity of resources, thereby its limitation is arranged.
Patent No. CN100999401A adopts barite and lead powder to improve shielding property, and same the existence needs the control construction technology, the shortcoming that barite and lead powder can not widespread adoption, thereby have limitation.
Summary of the invention:
Technical problem to be solved by this invention is to provide a kind of radiation shield concrete and preparation method thereof at the deficiencies in the prior art, and this radiation shield concrete shielding gamma-rays is respond well; Preparation technology is simple, the starting material wide material sources.
For solving the problems of the technologies described above, the technical solution used in the present invention is:
A kind of radiation shield concrete, it is characterized in that: comprise consolidating material, coarse aggregate, fine aggregate, steel fiber, high efficiency water reducing agent and water, described consolidating material is made up of ordinary Portland cement and inorganic mineral adulterant, and described inorganic mineral adulterant is silicon ash and flyash; Described fine aggregate is natural sand, boron glass powder and steel-making slag powder; Described coarse aggregate is the mixture of steel section or steel section and slag, the ratio of each component is: consolidating material 500kg/m
3, coarse aggregate 1400～2215kg/m
3, fine aggregate 750～950kg/m
3, water 155～200kg/m
3, high efficiency water reducing agent is 0.5～1.0% of consolidating material gross weight by weight, steel fiber is 1.0～1.5% of concrete cumulative volume by volume; Wherein: each components based on weight percentage in the consolidating material: ordinary Portland cement 75～80%, silicon ash 10%, flyash 10～15%; When coarse aggregate was the mixture of steel section and slag, the weight ratio of steel section and slag was 1: 1; Each components based on weight percentage in the fine aggregate: boron glass powder 15%～20%, steel-making slag powder 10～15%, natural sand 65～75%.
Press such scheme, described ordinary Portland cement is 42.5 grades of ordinary Portland cements; The consumption of ordinary Portland cement requires decision according to required concrete batching strength grade.
Press such scheme, described flyash is common secondary ash; Described silica flour is common silica flour, and specific surface area is 150000～250000m
2/ kg.
Press such scheme, the particle diameter of described coarse aggregate is 5～20mm.
Press such scheme, described steel-making slag powder is earlier slag to be deposited to the volume stability ball milling to 1～15 μ m again, and described volume stability is to detect according to national standard " steel-making slag powder (GB/T20491-2006) that is used for cement and concrete ".
Press such scheme, the boron glass powder that described boron glass powder is particle diameter≤1.18mm.
Press such scheme, described natural sand is natural river sand, and silt content is not more than 2%, and fineness modulus is 2.5～3.0.
Press such scheme, described steel fiber is characterized as: steel fiber length is 25～50mm, and diameter of section is 0.3～0.8mm, and length-to-diameter ratio is 55～85.
Press such scheme, the water-reducing rate of described high efficiency water reducing agent is more than 25%, to be preferably polycarboxylic acid series high efficiency water reducing agent.
The preparation method of above-mentioned radiation shield concrete is characterized in that: may further comprise the steps:
(1) by the ratio of each component is: consolidating material 500kg/m
3, coarse aggregate 1400～2215kg/m
3, fine aggregate 750～950kg/m
3, water 155～200kg/m
3, high efficiency water reducing agent is 0.5～1.0% of consolidating material gross weight by weight, steel fiber is 1.0～1.5% of concrete cumulative volume by volume; Wherein: each components based on weight percentage in the consolidating material: ordinary Portland cement 75～80%, silicon ash 10%, flyash 10～15%; When coarse aggregate was the mixture of steel section and slag, the weight ratio of steel section and slag was 1: 1; Each components based on weight percentage in the fine aggregate: boron glass powder 15%～20%, steel-making slag powder 10～15%, natural sand 65～75%., choose raw material;
(2) consolidating material, coarse aggregate and fine aggregate are poured into carried out mechanical stirring 2～3min in the stirrer, add steel fiber, mechanical stirring 2～3min, steel fiber is fully disperseed, and then adding the high efficiency water reducing agent mix and the mixing solutions of water, mechanical stirring 2～3min obtains mixture paste, mixture paste is injected the mould moulding of vibrating, and maintenance promptly.
Principle of the present invention is:
Coarse aggregate steel section, slag are heavy weight aggregates among the present invention, it had both satisfied can provide the shielding gamma-rays needed big density requirements, the coarse aggregate barite that can overcome common employing again is crisp because of property, easy powdering and influence concrete workability and strength problem in stirring, and compare wide material sources with barite; The boron glass powder of admixture can be recycled from the scrap glass slag of glasswork and obtain, thereby reduces the demand to natural mineral, can shield neutron ray effectively, reaches radioprotective effect preferably, and little to the influence of concrete strength.The mineral admixture of admixture can reduce concrete water-cement ratio, reduce the concrete shrinkage rate, improve concrete density and concrete cracking resistance ability, wherein: the main component of flyash is a kind of microglass bead body, it has good shape effect, it is joined in the mortar on the one hand can improve its workability, can also improve the water tolerance of gypsum on the other hand, reduce the heat release of hydrated cementitious hardened and shrink; The silica flour of admixture can improve the microstructure of hardened cement paste as a kind of complementary gelling material, major cause is: at first: silica flour has very high pozzolanic activity, be that silica flour itself with water hydration does not take place basically, but it can be at hydrated cementitious product C a (OH)
2And the secondary hydration reaction takes place under the excitation of some other compounds and generate the product with gelling; Secondly, silica flour possesses the micro-aggregate characteristic, and this not only makes the harmful hole that himself can fill in the hardened cement paste, and its secondary hydration product also can be filled the harmful hole in the hardened cement paste, thereby improve the hardened cement paste pore texture, improve compactness; The steel-making slag powder particle diameter of admixture is 1～15 μ m, can effectively fill the space between inorganic mineral adulterant and the aggregate after it mixes, and improves concrete density, can reduce the pollution of slag waste to environment again.The steel fiber of admixture can overcome the segregation of heavy aggregate preferably.
Beneficial effect of the present invention: (1) this radiation shield concrete has good mechanical performance and excellent endurance quality, and gamma-rays is had good shield effectiveness, and the shielding neutron ray is effective; (2) preparation method's technology of this radiation shield concrete is simple, and the starting material wide material sources are with low cost, but the comprehensive reutilization refuse reduces environmental pollution.
Embodiment
For a better understanding of the present invention, further illustrate content of the present invention, but content of the present invention not only is confined to the following examples below in conjunction with following examples.
The preparation method of embodiment 1～6 one kind of radiation shield concrete
1) with preparation 1m
3Radiation shield concrete is an example, chooses starting material according to the proportioning in the table 1, and each starting material is specific as follows:
Cement: select 42.5 grades of ordinary Portland cements for use.
The inorganic mineral adulterant: wherein flyash is common secondary ash; Silica flour is common silica flour, and specific surface area is 150000～250000m
2/ kg;
Coarse aggregate: the steel section, cylindric, particle diameter 5～18mm, diameter is 3～8mm, maximum length is no more than 15～20mm, apparent density 7500kg/m
3Slag: deposited 1 year, through press steaming stability check (steel-making slag powder (GB/T 20491-2006) that is used for cement and concrete with reference to National Standard "), Hubei Province steel slag of steady quality (mass loss≤5%), grating 5～20mm, apparent density is 2912kg/m3, and tap density is 1743kg/m
3, water-intake rate is 4.0%, diameter 10mm, length 10～20mm;
Natural sand: be natural river sand, silt content is not more than 2%, and fineness modulus is 2.5～3.0;
Steel-making slag powder: slag is deposited to the volume stability (detecting according to national standard " steel-making slag powder (GB/T20491-2006) that is used for cement and concrete ") ball milling to 1～15 μ m (median size 10 μ m) again;
The boron glass powder: the boron glass powder is levigate with it by mortar, be that the square hole sieve of 1.18mm sieves with sieve diameter, the boron glass powder of getting the lower part of screen branch and be particle diameter≤1.18mm is standby;
High efficiency water reducing agent: described high efficiency water reducing agent is a polycarboxylic acid series high efficiency water reducing agent, and water-reducing rate is more than 25%;
Steel fiber: length is 25～50mm, and diameter of section is 0.3～0.8mm; Length-to-diameter ratio is 55～85, density 7830kg/m
3
The composition of raw materials of radiation shield concrete among the table 1 embodiment 1-6
| Material component | Embodiment 1 | Embodiment 2 | Embodiment 3 | Embodiment 4 | Embodiment 5 | Embodiment 6 |
| Water (kg) | 155 | 155 | 175 | 185 | 200 | 200 |
| Cement (kg) | 400 | 375 | 400 | 400 | 375 | 400 |
| Silica flour (kg) | 50 | 50 | 50 | 50 | 50 | 50 |
| Flyash (kg) | 50 | 75 | 50 | 50 | 75 | 50 |
| Steel-making slag powder (kg) | 140 | 85 | 142 | 75 | 90 | 105 |
| Boron glass powder (kg) | 190 | 130 | 145 | 150 | 130 | 115 |
| Natural sand (kg) | 620 | 635 | 663 | 525 | 530 | 530 |
| Forging (kg) | 2215 | 2044 | 700 | 700 | 728 | 728 |
| Slag (kg) | 0 | 0 | 700 | 700 | 728 | 728 |
| Steel fiber (kg) | 78.5 | 117 | 109 | 78 | 92 | 109 |
| Water reducer (kg) | 5 | 4 | 5 | 5 | 3 | 5 |
(2) pour cement, inorganic mineral adulterant, coarse aggregate, the fine aggregate chosen in the step (1) in stirrer mechanical stirring 2～3min successively, add steel fiber, continue mechanical stirring 2～3min, make steel fiber can evenly spread in the compound, mixing solutions with the high efficiency water reducing agent that mixes and water adds stirrer then, restir 2～3min, obtain the concrete slurry, the slurry that stirs is injected mould, the moulding of vibrating, certain maintenance in the length of time is passed through in normal curing demoulding after a day at last, promptly gets radiation shield concrete.The radiation shield concrete fundamental property that makes according to the method for embodiment 1～6 sees Table 2, shields gamma-ray performance and sees Table 3.
The fundamental property of radiation shield concrete among the table 2 embodiment 1-6
| Performance index | Embodiment 1 | Embodiment 2 | Embodiment 3 | Embodiment 4 | Embodiment 5 | Embodiment 6 |
| Apparent density (kg/m 3) | 4258 | 4065 | 3235 | 3225 | 3241 | 3337 |
| 3d ultimate compression strength/MPa | 53.6 | 50.6 | 46.5 | 36.2 | 39.2 | 37.8 |
| 28d ultimate compression strength/MPa | 83.7 | 79.6 | 75.4 | 60.7 | 63.4 | 64.2 |
Concrete mainly is by testing it gamma-ray linear absorption coefficient to be characterized to gamma-ray shielding property.Usually the gamma-rays radioactive source is
60Co,
137Cs.With embodiment 1-6 according to the as above 300mm * 300mm of method moulding * 100mm concrete slab normal curing 28 days, with
60Co is a radioactive source, and its activity 25.0mCi adopts the little detection instrument of FJ-347A type X-γ gauge, at the positive identity distance radioactive source of concrete slab 40cm, the back side is under the condition of detection instrument 5cm, and the absorbed dose rate of test concrete slab sees Table 3 through calculating half decay thickness and linear absorption coefficient again.
Radiation shield concrete is to gamma-ray shielding property among the table 3 embodiment 1-6
By the data in the table 3 as can be seen, the radiation shield concrete of embodiment 1～6 preparation has good shield effectiveness to gamma-rays.
The mensuration of radiation shield concrete crystal water content and boron content among the table 4 embodiment 1-6
By table 4 as can be known: the radiation shield concrete of embodiment 1～6 preparation contains have an appointment 0.7% boron content and about 2.0% crystal water content.Because neutron is not charged, thus not with atom extranuclear interaction of electrons, and can only interact with nucleus.And neutron mass and proton are very approaching, shield sorption preferably so material such as the higher paraffin of hydrogen content, polyethylene, polypropylene and the materials such as boron oxide, boric acid and norbide that contain boron have neutron ray.In conjunction with existing achievement in research [" The Advance in Study on Radiation-proof Shielding " (Liu Xiankun, Dai Junlong, Hu Chunming etc., the 20th the 6th phase of volume of material Leader 2006.6); " energetic ray and shielding material thereof " (Liu Xiankun, Liu Ying etc., the 13rd the 1st phase of volume of Metallic Functional Materials 2006.2); " shielding concrete material property experimental study " (5 Chongmings, Ding Dexin etc., the 12nd phase of concrete 2007); " experimental study of radiation shield concrete " (Wang Ping, Wang Fuchuan etc., the 3rd 2 phases of volume of material of construction journal 2000.6)] expression: the radiation shield concrete that this embodiment 1～6 makes also has good shield effectiveness to neutron ray.
Claims (10)
1. radiation shield concrete, it is characterized in that: comprise consolidating material, coarse aggregate, fine aggregate, steel fiber, high efficiency water reducing agent and water, described consolidating material is made up of ordinary Portland cement and inorganic mineral adulterant, and described inorganic mineral adulterant is silicon ash and flyash; Described fine aggregate is natural sand, boron glass powder and steel-making slag powder; Described coarse aggregate is the mixture of steel section or steel section and slag, the ratio of each component is: consolidating material 500 kg/m
3, coarse aggregate 1400～2215 kg/m
3, fine aggregate 750～950 kg/m
3, water 155～200 kg/m
3, high efficiency water reducing agent is 0.5～1.0% of consolidating material gross weight by weight, steel fiber is 1.0～1.5% of concrete cumulative volume by volume; Wherein: each components based on weight percentage in the consolidating material: ordinary Portland cement 75～80%, silicon ash 10%, flyash 10～15%; When coarse aggregate was the mixture of steel section and slag, the weight ratio of steel section and slag was 1:1; Each components based on weight percentage in the fine aggregate: boron glass powder 15%～20%, steel-making slag powder 10～15%, natural sand 65～75%.
2. radiation shield concrete according to claim 1 is characterized in that: described ordinary Portland cement is 42.5 grades of ordinary Portland cements.
3. radiation shield concrete according to claim 1 is characterized in that: described flyash is common secondary ash; Described silica flour is common silica flour, and specific surface area is 150000～250000m
2/ kg.
4. radiation shield concrete according to claim 1 is characterized in that: the particle diameter of described coarse aggregate is 5～20mm.
5. radiation shield concrete according to claim 1 is characterized in that: described steel-making slag powder is earlier slag to be deposited to the volume stability ball milling to 1～15 μ m again.
6. radiation shield concrete according to claim 1 is characterized in that: the boron glass powder that described boron glass powder is particle diameter≤1.18mm.
7. radiation shield concrete according to claim 1 is characterized in that: described natural sand is natural river sand, and silt content is not more than 2%, and fineness modulus is 2.5～3.0.
8. radiation shield concrete according to claim 1 is characterized in that: described steel fiber is characterized as: steel fiber length is 25～50mm, and diameter of section is 0.3～0.8mm, and length-to-diameter ratio is 55～85.
9. radiation shield concrete according to claim 1 is characterized in that: described high efficiency water reducing agent is a polycarboxylic acid series high efficiency water reducing agent, and water-reducing rate is more than 25%.
10. the preparation method of radiation shield concrete according to claim 1 is characterized in that: may further comprise the steps:
(1) by the ratio of each component is: consolidating material 500 kg/m
3, coarse aggregate 1400～2215 kg/m
3, fine aggregate 750～950 kg/m
3, water 155～200 kg/m
3, high efficiency water reducing agent is 0.5～1.0% of consolidating material gross weight by weight, steel fiber is 1.0～1.5% of concrete cumulative volume by volume; Wherein: each components based on weight percentage in the consolidating material: ordinary Portland cement 75～80%, silicon ash 10%, flyash 10～15%; When coarse aggregate was the mixture of steel section and slag, the weight ratio of steel section and slag was 1:1; Each components based on weight percentage in the fine aggregate: boron glass powder 15%～20%, steel-making slag powder 10～15%, natural sand 65～75% is chosen raw material;
(2) consolidating material, coarse aggregate and fine aggregate are poured into carried out mechanical stirring 2～3min in the stirrer, add steel fiber, mechanical stirring 2～3min, steel fiber is fully disperseed, and then adding the high efficiency water reducing agent mix and the mixing solutions of water, mechanical stirring 2～3min obtains mixture paste, mixture paste is injected the mould moulding of vibrating, and maintenance promptly.
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