CN109592952A - A kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete - Google Patents

A kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete Download PDF

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Publication number
CN109592952A
CN109592952A CN201910026868.1A CN201910026868A CN109592952A CN 109592952 A CN109592952 A CN 109592952A CN 201910026868 A CN201910026868 A CN 201910026868A CN 109592952 A CN109592952 A CN 109592952A
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nuclear power
sulphoaluminate cement
high latitude
radiation type
cement base
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CN201910026868.1A
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CN109592952B (en
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程新
徐信刚
王守德
李树森
赵丕琪
芦令超
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University of Jinan
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University of Jinan
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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
    • C04B28/06—Aluminous cements
    • 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
    • C04B7/00—Hydraulic cements
    • C04B7/32—Aluminous cements
    • C04B7/323—Calcium aluminosulfate cements, e.g. cements hydrating into ettringite
    • 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
    • C04B2201/00—Mortars, concrete or artificial stone characterised by specific physical values
    • C04B2201/20—Mortars, concrete or artificial stone characterised by specific physical values for the density
    • 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
    • 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
    • C04B2201/52—High compression strength concretes, i.e. with a compression strength higher than about 55 N/mm2, e.g. reactive powder concrete [RPC]
    • 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
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P40/00—Technologies relating to the processing of minerals
    • Y02P40/10—Production of cement, e.g. improving or optimising the production methods; Cement grinding

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  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Ceramic Engineering (AREA)
  • Materials Engineering (AREA)
  • Structural Engineering (AREA)
  • Organic Chemistry (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Inorganic Chemistry (AREA)
  • Curing Cements, Concrete, And Artificial Stone (AREA)

Abstract

The invention discloses a kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete, the mass percentage composition of the concrete is as follows: Boron-Based Fuel-Rich barium sulphoaluminate cement clinker 15~30%, water 5-15%, fine aggregate 20~40%, coarse aggregate 35~65%, additive 0.11~1%.High latitude region of the invention has excellent anti-freezing property with Anti-radiation type sulphoaluminate cement base nuclear power concrete, and because it contains a large amount of barium element, boron element, heavy metal element and a large amount of crystallization water, it can not only effectively shielding protection α, β, γ, X-ray, and absorbable protection neutron irradiation；Boron-Based Fuel-Rich barium sulphate aluminium cement used also contains barium element, ferro element, γ, X-ray can effectively be protected, and cement durability is good, compact structure, cement density is big, can effectively prevent due to aggregate it is overweight caused by segregation phenomenon, can be very good to apply the nuclear power engineering in high latitude cold region.

Description

A kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete
Technical field
The present invention relates to a kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete, belong to extraordinary coagulation Native field.
Background technique
It is new energy there is the area differentiations big, energy density of representative with wind energy, solar energy, water energy, biological energy source etc. It is low, power generation stabilization is poor leads to the second-rate of electric energy.Compared with above-mentioned new energy, nuclear energy has cleaning, low-carbon, high energy The clear superiorities such as metric density, lasting, stable, have huge Development volue and good development potentiality.
As a kind of emerging clean energy resource --- nuclear energy is just being widely used in nuclear power, military affairs, education, scientific research and medical treatment etc. Various fields, but pollution caused by nuclear radiation becomes an overall situation problem of facing mankind again.Radiation pollution has become after water The fourth-largest pollution after pollution, atmosphere pollution, noise pollution.People, which is exposed in radiation environment, will appear fatigue, giddy, white blood The different degrees of radiation disease symptoms such as disease, or even also will increase cancer, distortion, heredity lesion incidence, seriously affect the mankind Health；Is there is distortion and strange plant by excessive radiation meeting inducing plant cell chromosome DNA mutation in plant, into And lead to the death of plant.To realize that the following nuclear energy uses efficiently, safe are not only faced with the maximization in nuclear reaction service life, first Into nuclear reaction material and the safe and efficient three challenges for utilizing nuclear reaction material, also urgent need it is novel, efficient, safe Radiation proof material.Radiation proof material is related to nuclear reaction production, the radiation such as generated nuclear radiation, nuclear waste is dirty in use process Dye can safety shielding, be that key points and difficulties that Nuclear Science and Technology further develop and nuclear technology are used widely One of the prerequisite.
Main shielding material currently used for protecting all kinds of rays have heavy metal stereotype, steel plate (ball, forging), water, polymer, Cement, concrete etc..Wherein, it heavy metal stereotype, steel plate (ball, forging), polymer higher cost and should not construct；Though water is at low cost But unsuitable machine-shaping and control；Comparatively, cement and Cost of Concrete is cheap and application property is good, is the ideal of radiation protection Material.But in high latitude extremely frigid zones, nuclear power concrete is easy to destroy concrete structure due to low temperature, leads to core spoke The leakage for penetrating even nuke rubbish, in turn results in environmental pollution, influences the health of people.Therefore it needs a kind of to can be resistant to high and cold be suitble to The radiation protection nuclear power concrete of high latitudes cold zone.
Summary of the invention
The present invention provides a kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete, concrete tools There are extremely strong shielding property, compact structure, hydrated product contains a large amount of crystallization water, can protect and absorb X-ray, gamma-rays And neutron irradiation, and there is excellent anti-freezing property, and cement density is big, and aggregate segregation phenomenon can be effectively prevented Occur.
The invention adopts the following technical scheme:
A kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete, it is by following mass percent Raw material is made: Boron-Based Fuel-Rich barium sulphoaluminate cement clinker 15~30%, water 5-15%, fine aggregate 20~40%, coarse aggregate 35~ 65%, additive 0.11~1%.
The mine phase mass percentage composition of the Boron-Based Fuel-Rich barium sulphoaluminate cement clinker are as follows: barium-bearing calcium sulfo-aluminate 48~ 65%, dicalcium ferrite 5~17%, dicalcium silicate 15~20%, barium aluminate 8~15%, line borate 3~8%.
The Raw meal oxidates mass percentage composition of the clinker: CaO 18~35%, BaO 20~35%, Fe2O3 1.3~3.5%, Al2O325~38%, B2O31.2~3.0%, SO36~12%, SiO25~9%.
The coarse aggregate is combination one or more in limonite ore, magnetic iron ore and witherite, and size is 10 ~30mm.
The fine aggregate is combination one or more in levigate blanc fixe, limonite ore and barium slag, and size exists 0.5~5mm.
The additive is made of adjustable solidification agent and water-reducing agent according to the weight ratio of 1:1~50, and wherein adjustable solidification agent is boric acid, Water-reducing agent is high performance water reducing agent of polyocarboxy acid.
The high performance water reducing agent of polyocarboxy acid solid content is not less than 20%, and water-reducing rate is not less than 20%.
A kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete of the invention, used raw material and Detection method meets the related standard of GB/T 34008-2017 radiation shield concrete.Cement used inherently has extremely strong Shielding property, compact structure, hydrated product contain a large amount of crystallization water, can protect and absorb X-ray, gamma-rays and neutron Radiation, and there is excellent anti-freezing property, and cement density is big, and the generation of aggregate segregation phenomenon can be effectively prevented.It mixes The coarse aggregate and fine aggregate added all aims at designed by radiation shield concrete, wherein contain boron, barium and a large amount of light element, There is very strong absorption shielding action to α, β, γ, X-ray and neutron ray, can be very good to apply in high latitude cold region Nuclear power engineering.
The beneficial effects of the present invention are: high latitude region of the invention Anti-radiation type sulphoaluminate cement base nuclear power concrete Because it contains a large amount of boron, barium and a large amount of light element and the crystallization water, have to α, β, γ, X-ray and neutron ray very strong Absorption shielding action；Magnetic iron ore and iron ore and witherite is thermally conductive in coarse aggregate and fine aggregate used in the present invention Coefficient is larger, and heat transfer caused by nuclear radiation can be gone out well, heat is avoided to have an impact concrete structure； Boron-Based Fuel-Rich barium sulphate aluminium cement used in the present invention also has good anti-freezing property, and barium element rich in, boron member Element and hydrated product contain a large amount of crystallization water, can effectively shield and absorb γ, X-ray and neutron ray, and cement is close Degree is big, can effectively avoid the generation of the segregation phenomenon of heavy aggregate.To sum up, it can be seen that use anti-in high latitude region of the invention Radial pattern sulphoaluminate cement base nuclear power concrete is a kind of excellent nuclear power for being suitble to high latitude cold region nuclear power engineering building Concrete.
Specific embodiment
The present invention is described in further detail combined with specific embodiments below.
Embodiment
In order to preferably study the property of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete of the invention Can, inventor devises several groups of embodiments of different ratio, and specific ingredient quality composition is as shown in table 1.Used raw material and Detection method meets the related standard of GB/T 34008-2017 radiation shield concrete.Working performance of concrete and anti-freezing property Testing result is as shown in table 2, table 3.In addition, two kinds of concrete test plate (panel)s are made according to 1 charge ratio of table, respectively have 300mm × 300mm × 150mm and 300mm × 300mm × 100mm.Sample is subjected to gamma-rays irradiation, detect and calculates its half-value layer thickness Spend δ1/2Linear absorption coefficient μ, experimental result are as shown in table 4 compared with normal concrete.
1 concrete batching table of table
2 working performance of concrete of table
3 coagulation anti-freezing property of table
The test of 4 concrete shield gamma-rays of table
By table 2, table 3 as it can be seen that the high latitude region is good with the workability of Anti-radiation type sulphoaluminate cement base nuclear power concrete Good, apparent density is all in 3500kg/m3More than, and the excellent construction for being suitable for use in high latitude region building of anti-freezing property.It can by table 4 To find out, for the same source γ, to make its radiation intensity decaying half, it is thick for No. 4 6.12~6.21cm of need of normal concrete, And the high latitude region only needs 2.92~3.10cm with Anti-radiation type sulphoaluminate cement base nuclear power concrete, illustrates of the invention High latitude region is prominent with the gamma-emitting ability of Anti-radiation type sulphoaluminate cement base nuclear power agent on crack resistance of concrete.In general the present invention is anti- Freeze performance and shielding property is excellent, is suitable for the construction of high latitude region nuclear power engineering.

Claims (7)

1. a kind of high latitude region Anti-radiation type sulphoaluminate cement base nuclear power concrete, which is characterized in that it is by following matter Amount percentage raw material be made: Boron-Based Fuel-Rich barium sulphoaluminate cement clinker 15~30%, water 5-15%, fine aggregate 20~40%, Coarse aggregate 35~65%, additive 0.11~1%.
2. high latitude region according to claim 1 Anti-radiation type sulphoaluminate cement base nuclear power concrete, feature exist In the mine phase mass percentage composition of the Boron-Based Fuel-Rich barium sulphoaluminate cement clinker are as follows: barium-bearing calcium sulfo-aluminate 48~65%, ferrous acid Dicalcium 5~17%, dicalcium silicate 15~20%, barium aluminate 8~15%, line borate 3~8%.
3. high latitude region according to claim 1 Anti-radiation type sulphoaluminate cement base nuclear power concrete, feature exist In the Raw meal oxidates mass percentage composition of the clinker: CaO 18~35%, BaO 20~35%, Fe2O3 1.3 ~3.5%, Al2O325~38%, B2O31.2~3.0%, SO36~12%, SiO25~9%.
4. high latitude region according to claim 1 Anti-radiation type sulphoaluminate cement base nuclear power concrete, feature exist In, the coarse aggregate be combination one or more in limonite ore, magnetic iron ore and witherite, size 10~ 30mm。
5. high latitude region according to claim 1 Anti-radiation type sulphoaluminate cement base nuclear power concrete, feature exist In, the fine aggregate be combination one or more in levigate blanc fixe, limonite ore and barium slag, size 0.5~ 5mm。
6. high latitude region according to claim 1 Anti-radiation type sulphoaluminate cement base nuclear power concrete, feature exist In the additive is made of adjustable solidification agent and water-reducing agent according to the weight ratio of 1:1~50, and wherein adjustable solidification agent is boric acid, diminishing Agent is high performance water reducing agent of polyocarboxy acid.
7. high latitude region according to claim 6 Anti-radiation type sulphoaluminate cement base nuclear power concrete, feature exist In the high performance water reducing agent of polyocarboxy acid solid content is not less than 20%, and water-reducing rate is not less than 20%.
CN201910026868.1A 2019-01-11 2019-01-11 Radiation-proof sulphoaluminate cement-based nuclear power concrete for high-latitude areas Active CN109592952B (en)

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Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110981361A (en) * 2019-12-25 2020-04-10 四川中核艾瑞特工程检测有限公司 Radiation-proof concrete with high H element content and preparation method thereof
CN113072341A (en) * 2021-04-15 2021-07-06 杨荣飞 Portland cement radiation-proof concrete and production process thereof

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2176221C2 (en) * 1999-11-01 2001-11-27 Пензенская государственная архитектурно-строительная академия Composition for building article making
CN102701613A (en) * 2012-06-18 2012-10-03 湖北大学 Preparation method of radiation-proof cement clinker mineral phase system
CN103224369A (en) * 2013-04-09 2013-07-31 四川省交通运输厅公路规划勘察设计研究院 Anti-radiation concrete produced from slag aggregate, and production method thereof
CN107021711A (en) * 2017-04-25 2017-08-08 济南大学 A kind of nuclear power engineering cement concrete

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2176221C2 (en) * 1999-11-01 2001-11-27 Пензенская государственная архитектурно-строительная академия Composition for building article making
CN102701613A (en) * 2012-06-18 2012-10-03 湖北大学 Preparation method of radiation-proof cement clinker mineral phase system
CN103224369A (en) * 2013-04-09 2013-07-31 四川省交通运输厅公路规划勘察设计研究院 Anti-radiation concrete produced from slag aggregate, and production method thereof
CN107021711A (en) * 2017-04-25 2017-08-08 济南大学 A kind of nuclear power engineering cement concrete

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
胡曙光: "《特种水泥》", 31 January 2010, 武汉理工大学出版社 *
马一平: "《建筑功能材料》", 31 March 2014, 同济大学出版社 *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110981361A (en) * 2019-12-25 2020-04-10 四川中核艾瑞特工程检测有限公司 Radiation-proof concrete with high H element content 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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