CN114031353A - Neutron radiation prevention boron carbide concrete and preparation method thereof - Google Patents

Neutron radiation prevention boron carbide concrete and preparation method thereof Download PDF

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CN114031353A
CN114031353A CN202111612402.3A CN202111612402A CN114031353A CN 114031353 A CN114031353 A CN 114031353A CN 202111612402 A CN202111612402 A CN 202111612402A CN 114031353 A CN114031353 A CN 114031353A
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boron carbide
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Inventor
付海龙
罗太忠
汪映红
王保林
刘锷
柳涛
马亚刚
史金旭
田子琪
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China Nuclear Industry 24 Construction Co Ltd
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    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B28/00Compositions of mortars, concrete or artificial stone, containing inorganic binders or the reaction product of an inorganic and an organic binder, e.g. polycarboxylate cements
    • C04B28/02Compositions 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
    • C04B28/04Portland cements
    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B14/00Use of inorganic materials as fillers, e.g. pigments, for mortars, concrete or artificial stone; Treatment of inorganic materials specially adapted to enhance their filling properties in mortars, concrete or artificial stone
    • C04B14/02Granular materials, e.g. microballoons
    • C04B14/32Carbides; Nitrides; Borides ; Silicides
    • C04B14/322Carbides
    • C04B14/323Boron carbide
    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B2111/00Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
    • C04B2111/00474Uses not provided for elsewhere in C04B2111/00
    • C04B2111/00862Uses not provided for elsewhere in C04B2111/00 for nuclear applications, e.g. ray-absorbing concrete
    • CCHEMISTRY; METALLURGY
    • C04CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04BLIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B2201/00Mortars, concrete or artificial stone characterised by specific physical values
    • C04B2201/50Mortars, concrete or artificial stone characterised by specific physical values for the mechanical strength

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

Abstract

The invention discloses a neutron radiation prevention boron carbide concrete and a preparation method thereof, wherein the neutron radiation prevention boron carbide concrete comprises the following components in parts by weight: fine aggregate: 383 parts of; coarse aggregate: 1142 parts of a carrier; water: 175-180 parts of a modifier; the water reducing agent accounts for 1 to 1.2 percent of the weight of the gel material; cement: 295-325 parts; fly ash: 46 parts of (a); slag powder: 86 parts of a binder; boron carbide: 220-300 parts; the method comprises the steps of pouring coarse aggregate, fine aggregate, fly ash and slag powder into a stirring tank in sequence; pouring boron carbide and cement into a stirring tank in sequence; starting the stirring tank, and stirring for a second set time; pouring water and a water reducing agent into a stirring tank; starting the stirring tank, and continuously stirring according to the set stirring speed and the third set time; by using boron carbide as a shielding and controlling material of concrete, the volume weight of the concrete can be reduced on the premise of ensuring the radiation-proof performance of the concrete under the condition of using conventional fine aggregate and coarse aggregate, and the concrete can be ensured to have better fluidity and pumpability.

Description

Neutron radiation prevention boron carbide concrete and preparation method thereof
Technical Field
The invention relates to the technical field of neutron radiation prevention special concrete construction, in particular to neutron radiation prevention boron carbide concrete and a preparation method thereof.
Background
In the protection of nuclear reactor, particle accelerator and radioactive isotope equipment in industrial, agricultural and scientific research departments, the concrete for shielding X-ray, gamma-ray and neutron radiation action is usually heavy radiation-proof shielding concrete, the cementing material is usually silicate cement with low hydration heat or special cement such as high alumina cement, barium cement, magnesia cement, etc., and the aggregate is usually barite, magnetite, limonite, waste iron block, etc.
Such concrete has a large volume weight, resulting in insufficient fluidity and pumpability, and is inconvenient for continuous construction.
Disclosure of Invention
The invention aims to solve the technical problems of large volume weight, and insufficient fluidity and pumpability of the radiation-proof concrete at the present stage, and aims to provide the neutron radiation-proof boron carbide concrete and the preparation method thereof, so as to solve the problem of how to realize effective radiation protection under the condition of reducing the volume weight of the concrete.
The invention is realized by the following technical scheme:
the neutron radiation prevention boron carbide concrete comprises the following components in parts by weight:
gel material: 647-757 parts;
fine aggregate: 383 parts of;
coarse aggregate: 1142 parts of a carrier;
water: 175-180 parts of a modifier;
the water reducing agent accounts for 1-1.2% of the gel material;
the gel material comprises the following components in parts by weight:
cement: 295-325 parts;
fly ash: 46 parts of (a);
slag powder: 86 parts of a binder;
boron carbide: 220-300 parts.
Preferably, the cement is portland cement, the strength grade is 42.5, and the specific surface area is 300-360 cm2/g, loss on ignition is less than or equal to 5.0 percent.
Preferably, the particle size of the boron carbide is 0-3 mm, the purity is more than or equal to 95%, the sieving rate is more than or equal to 98%, the mud content is less than or equal to 3.0%, the mud block content is less than or equal to 1.0%, and the fineness modulus is 1.9.
Specifically, the fly ash is class II F fly ash, the fineness is less than or equal to 25.0%, the water demand ratio is less than or equal to 105%, the loss on ignition is less than or equal to 8.0%, and the sulfur trioxide content is less than or equal to 3.0%.
Preferably, the slag powder is above grade S95, and the specific surface area is as follows: 400-500 m2Kg, density is more than or equal to 2.8g/cm3The fluidity ratio is more than or equal to 95 percent, the ignition loss is less than or equal to 3.0 percent, the sulfur trioxide content is less than or equal to 4.0 percent, the activity index in 7 days is more than or equal to 75 percent, and the activity index in 28 days is more than or equal to 95 percent.
Specifically, the fine aggregate is natural II medium sand, the fineness modulus is 2.3-3.0, the mud content is less than or equal to 3.0%, the mud block content is less than or equal to 1.0%, the water absorption is less than or equal to 2%, and the bulk density is more than or equal to 1400kg/m3Apparent density is more than or equal to 2500kg/m3The porosity is less than or equal to 44 percent;
the coarse aggregate is crushed stone which is II-class continuous graded crushed stone with the maximum grain diameter of 5-25 mm, the compact void ratio is less than or equal to 45 percent, the mud content is less than or equal to 1.0 percent, the mud block content is less than or equal to 0.2 percent, and the apparent density is more than or equal to 2600kg/m3The crushing index value is less than or equal to 20 percent, and the needle sheet content is less than or equal to 10 percent.
Preferably, the water reducing agent is a polycarboxylic acid high-performance water reducing agent, the water reducing rate is more than or equal to 25 percent, the gas content is less than or equal to 6.0 percent, the bleeding rate ratio is less than or equal to 50 percent, and the pressure bleeding rate ratio is less than or equal to 90 percent.
Preferably, the parameters of the water meet that the pH value is more than or equal to 4.5, the chloride ion is less than or equal to 1000mg/L, the sulfate ion is less than or equal to 2000mg/L, the insoluble substance is less than or equal to 2000mg/L, and the soluble substance is less than or equal to 5000 mg/L.
As a preferred embodiment, the concrete comprises the following components in parts by weight:
gel material: 700 parts of (1);
fine aggregate: 383 parts of;
coarse aggregate: 1142 parts of a carrier;
water: 175 parts of a lubricant;
water reducing agent: 7.5 parts;
the gel material comprises the following components in parts by weight:
cement: 308 parts of (A);
fly ash: 46 parts of (a);
slag powder: 86 parts of a binder;
boron carbide: 260 parts of (A).
A preparation method of neutron radiation prevention boron carbide concrete comprises the following steps:
pouring the coarse aggregate, the fine aggregate, the fly ash and the slag powder into a stirring tank in sequence;
starting the stirring tank, and stirring for a first set time;
pouring boron carbide and cement into a stirring tank in sequence;
starting the stirring tank, and stirring for a second set time;
pouring water and a water reducing agent into a stirring tank;
starting the stirring tank, and continuously stirring according to the set stirring speed and the third set time.
Compared with the prior art, the invention has the following advantages and beneficial effects:
according to the invention, boron carbide is used as a shielding and controlling material of the concrete, and under the condition of using conventional fine aggregate and coarse aggregate, the volume weight of the concrete can be reduced on the premise of ensuring the radiation-proof performance of the concrete, so that the concrete has better fluidity and pumpability, and the continuity of construction is facilitated;
meanwhile, the molecular formula of boron carbide is relatively stable, and compared with the radiation protection performance realized by using certain radioactive ray shielding composite materials, the boron carbide can effectively solve the problems of insufficient mechanical property and corrosion resistance and the like of the existing radioactive ray shielding composite materials, has better durability and prolongs the service life.
Drawings
The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate exemplary embodiments of the invention and together with the description serve to explain the principles of the invention.
FIG. 1 is a flow chart of a preparation method of neutron radiation prevention boron carbide concrete according to the invention.
Detailed Description
In order to make the objects, technical solutions and advantages of the present invention more apparent, the present invention will be further described in detail with reference to the accompanying drawings and embodiments. It is to be understood that the specific embodiments described herein are for purposes of illustration only and are not to be construed as limitations of the invention.
It should be noted that, for convenience of description, only the portions related to the present invention are shown in the drawings.
In the present invention, the embodiments and features of the embodiments may be combined with each other without conflict. The present invention will be described in detail below with reference to the accompanying drawings in conjunction with embodiments.
Example one
The embodiment provides neutron radiation prevention boron carbide concrete which comprises the following components in parts by weight:
gel material: 647-757 parts; fine aggregate: 383 parts of; coarse aggregate: 1142 parts of a carrier; water: 175-180 parts of a modifier; the water reducing agent accounts for 1 to 1.2 percent of the weight of the gel material;
the cementing material is a solid matter which can be changed into firm stone from slurry under the physical and chemical actions, and can be used for cementing other materials to make into a composite solid with a certain mechanical strength. In civil engineering materials, any material capable of bonding granular or block materials into a whole through a series of physical and chemical changes is called a gelled material. The gelled material is a material which can bond loose or blocky materials into a whole in the process of changing plastic slurry into hard stone through the physical and chemical actions of the gelled material.
The gel material in the embodiment comprises the following components in parts by weight: cement: 295-325 parts; fly ash: 46 parts of (a); slag powder: 86 parts of a binder; boron carbide: 220-300 parts.
By adding the material containing the boron element into the concrete and performing a mixing proportion test on the concrete, the special concrete which not only has compressive strength, admixture compatibility, initial setting time and the like which meet the use requirements, but also has good neutron radiation prevention effect is prepared.
In the embodiment, the cement is P.O42.5 grade ordinary portland cement, the strength grade is 42.5, and the specific surface area is 300-360 cm2/g, the ignition loss is less than or equal to 5.0 percent, and the flexural strength of the steel plate is not less than 3.5MPa in 3 days and not less than 6.5MPa in 28 days; the 3-day compressive strength is not less than 17.0MPa, and the 28-day compressive strength is not less than 42.5 MPa.
The particle size of the boron carbide is 0-3 mm, the purity is more than or equal to 95%, the sieving rate is more than or equal to 98%, the mud content is less than or equal to 3.0%, the mud block content is less than or equal to 1.0%, and the fineness modulus is 1.9.
The fly ash is class II F fly ash, the fineness is less than or equal to 25.0 percent, the water demand ratio is less than or equal to 105 percent, the ignition loss is less than or equal to 8.0 percent, and the sulfur trioxide content is less than or equal to 3.0 percent.
The slag powder is more than S95 grade, and the specific surface area is as follows: 400-500 m2Kg, density is more than or equal to 2.8g/cm3The fluidity ratio is more than or equal to 95 percent, the ignition loss is less than or equal to 3.0 percent, the sulfur trioxide content is less than or equal to 4.0 percent, the activity index in 7 days is more than or equal to 75 percent, and the activity index in 28 days is more than or equal to 95 percent.
The fine aggregate is natural medium sand II, the fineness modulus is 2.3-3.0, the mud content is less than or equal to 3.0%, the mud block content is less than or equal to 1.0%, the water absorption rate is less than or equal to 2%, and the bulk density is more than or equal to 1400kg/m3Apparent density is more than or equal to 2500kg/m3The porosity is less than or equal to 44 percent, and the content of organic matters is lighter than the physical property index requirement of standard color.
The coarse aggregate is crushed stone which is II-class continuous graded crushed stone with the maximum grain diameter of 5-25 mm, the compact void ratio is less than or equal to 45 percent, the mud content is less than or equal to 1.0 percent, the mud block content is less than or equal to 0.2 percent, and the apparent density is more than or equal to 2600kg/m3The crushing index value is less than or equal to 20 percent, and the needle sheet content is less than or equal to 10 percent.
The water reducing agent is a polycarboxylic acid high-performance water reducing agent, the water reducing rate is more than or equal to 25 percent, the gas content is less than or equal to 6.0 percent, the bleeding rate ratio is less than or equal to 50 percent, the pressure bleeding rate ratio is less than or equal to 90 percent, and the change amount over time within one hour is less than or equal to 45 mm.
The water is fresh water, the pH value is more than or equal to 4.5, the chloride ion is less than or equal to 1000mg/L, the sulfate ion is less than or equal to 2000mg/L, the insoluble substance is less than or equal to 2000mg/L, and the soluble substance is less than or equal to 5000 mg/L.
Example two
The embodiment is a preferable example based on the first embodiment, and the neutron radiation prevention boron carbide concrete in the embodiment comprises the following components in parts by weight:
gel material: 700 parts of (1); fine aggregate: 383 parts of; coarse aggregate: 1142 parts of a carrier; water: 175 parts of a lubricant; water reducing agent: 7.5 parts;
the gel material comprises the following components in parts by weight: cement: 308 parts of (A); fly ash: 46 parts of (a); slag powder: 86 parts of a binder; boron carbide: 260 parts of (A).
The weight components are obtained by tests, specific test data being listed below.
Experiment one
The raw materials are as follows according to the parts by weight:
Figure BDA0003435854950000061
Figure BDA0003435854950000071
wherein, the sand rate is the percentage of the mass of sand in the concrete to the total mass of sand and stone, and the change of the sand rate can obviously change the total surface area of the aggregate, thereby having great influence on the workability of the concrete mixture.
The principle of determining the sand rate is as follows: on the premise of ensuring the cohesiveness and the fluidity of the concrete mixture, the cement paste has the optimal sand rate which is time-saving and optimal.
Variations in sand rate can affect the gradation of aggregate in fresh concrete, causing a large variation in the void fraction and total surface area of the aggregate, with a significant impact on the workability of the fresh concrete. When the amount of the cement paste is fixed, the sand rate is too large, the total surface area and the void ratio of aggregate are increased, more cement paste is required to be filled and wrapped to aggregate, so that the cement paste with the lubricating effect is reduced, and the flowability of fresh concrete is reduced. The sand rate is too small, the void ratio of the aggregate is obviously increased, an enough mortar layer cannot be ensured between the coarse aggregate, the flowability of fresh concrete can be reduced, the cohesiveness and the water retention property can be seriously influenced, and the phenomena of segregation, slurry flow and the like are easily caused.
The water-cement ratio refers to the ratio of water consumption per cubic meter of concrete to the amount of all cement materials.
And (3) analysis results: when the sand rate is 36%, the water consumption is 160, and the water-cement ratio is 0.43, the compressive strength of the concrete is gradually increased along with the continuous increase of the boron carbide dosage, the strength is highest at 280, and then the compressive strength of the concrete is gradually reduced along with the increase of the boron carbide dosage.
When the sand rate is 38%, the water consumption is 175%, the water-cement ratio is 0.40, and the admixture addition amount is 1.5%, the concrete compressive strength is gradually increased along with the continuous increase of the boron carbide dosage, the strength is highest when the boron carbide dosage is about 300, and then the concrete compressive strength is gradually reduced along with the increase of the boron carbide dosage.
Experiment two
The raw materials are as follows according to the parts by weight:
Figure BDA0003435854950000081
Figure BDA0003435854950000091
and (3) analysis results: when the sand rate is 40%, the water consumption is 175, the water-cement ratio is 0.40, and the admixture mixing amount is 1.5%, the concrete slump is gradually reduced and the concrete workability is gradually deteriorated along with the continuous increase of the boron carbide dosage.
Experiment three
The raw materials are as follows according to the parts by weight:
Figure BDA0003435854950000092
Figure BDA0003435854950000101
and (3) analysis results: when the dosage of boron carbide is in the range of 220, 240 and 260, the 28-day compressive strength is the lowest when the sand rate is 38%. When the dosage of boron carbide is in the range of 280 to 300, the compressive strength is highest in 28 days when the sand rate is 38%.
By combining the data of the first experiment, the second experiment and the third experiment, the concrete with the best performance of 308 parts of cement, 175 parts of mixing water, 46 parts of fly ash, 86 parts of slag powder, 260 parts of boron carbide, 383 parts of fine aggregate, 1142 parts of coarse aggregate and 7.5 parts of polycarboxylic acid water reducer is determined to be the best concrete mixing ratio.
The verification proves that the concrete with the formula has optimal performance, can meet various performances, ensures that the concrete has good performances of fluidity, impermeability, folding resistance, compression resistance, frost resistance, shrinkage resistance and the like, also has good effect of shielding neutron rays, and each index of the concrete meets the technical requirement.
EXAMPLE III
In this embodiment, a neutron radiation prevention boron carbide concrete in the first embodiment and the second embodiment is provided, and therefore, compared with a common concrete, the concrete added with boron carbide has a different manufacturing process, and thus the embodiment provides a preparation method of the neutron radiation prevention boron carbide concrete, as shown in fig. 1, the preparation method includes:
first, screening the raw materials meeting the requirements of the parameters described in the first and second examples in advance, and weighing according to the set specific gravity value (in this example, the weight ratio in the second example is taken as an example)
Step two, pouring 1142 parts of coarse aggregate, 383 parts of fine aggregate, 46 parts of fly ash and 86 parts of slag powder into a stirring tank in sequence;
and thirdly, starting the stirring tank, and stirring for a first set time to preliminarily mix the coarse aggregate, the fine aggregate, the fly ash and the slag powder in the stirring tank.
In this embodiment, the first set time may be 20S, or the first set time may be 0 according to the time situation, that is, 1142 parts of coarse aggregate, 383 parts of fine aggregate, 46 parts of fly ash, and 86 parts of slag powder are poured, and then the fourth step is directly performed without stirring, so that the preparation time can be effectively saved.
Fourthly, pouring 260 parts of boron carbide and 308 parts of cement into a stirring tank in sequence;
and fifthly, starting the stirring tank, stirring for a second set time, and mixing the coarse aggregate, the fine aggregate, the fly ash, the slag powder, the water and the water reducing agent again.
In the embodiment, one of the second set time is preferably 20S, that is, 1142 parts of coarse aggregate, 383 parts of fine aggregate, 46 parts of fly ash, 86 parts of slag powder, 260 parts of boron carbide and 308 parts of cement are poured, and stirring is stopped after 20S.
Sixthly, pouring water and the water reducing agent into a stirring tank;
and step seven, starting the stirring tank, and continuously stirring according to the set stirring speed and the third set time.
In the embodiment, because boron carbide is used, the stirring time for preparing the boron carbide concrete is longer than that of common concrete, otherwise, the phenomena of 'dry material' at one end and 'thin material' at the other end occur locally, so that the optimal stirring time of the third set time is 180s, the optimal stirring speed is 150-350r/min, and the neutron radiation-proof high-performance concrete is obtained.
After the preparation of the boron carbide concrete is completed, continuous stirring is required to avoid the concrete from being coagulated.
In the description herein, reference to the description of the terms "one embodiment/mode," "some embodiments/modes," "example," "specific example," or "some examples," etc., means that a particular feature, structure, material, or characteristic described in connection with the embodiment/mode or example is included in at least one embodiment/mode or example of the application. In this specification, the schematic representations of the terms used above are not necessarily intended to be the same embodiment/mode or example. Furthermore, the particular features, structures, materials, or characteristics described may be combined in any suitable manner in any one or more embodiments/modes or examples. Furthermore, the various embodiments/aspects or examples and features of the various embodiments/aspects or examples described in this specification can be combined and combined by one skilled in the art without conflicting therewith.
Furthermore, the terms "first", "second" and "first" are used for descriptive purposes only and are not to be construed as indicating or implying relative importance or implicitly indicating the number of technical features indicated. Thus, a feature defined as "first" or "second" may explicitly or implicitly include at least one such feature. In the description of the present application, "plurality" means at least two, e.g., two, three, etc., unless specifically limited otherwise.
It will be understood by those skilled in the art that the foregoing embodiments are merely for clarity of description and are not intended to limit the scope of the invention. It will be apparent to those skilled in the art that other variations or modifications may be made on the above invention and still be within the scope of the invention.

Claims (10)

1. The neutron radiation prevention boron carbide concrete is characterized by comprising the following components in parts by weight:
gel material: 647-757 parts;
fine aggregate: 383 parts of;
coarse aggregate: 1142 parts of a carrier;
water: 175-180 parts of a modifier;
the water reducing agent accounts for 1-1.2% of the gel material;
the gel material comprises the following components in parts by weight:
cement: 295-325 parts;
fly ash: 46 parts of (a);
slag powder: 86 parts of a binder;
boron carbide: 220-300 parts.
2. The neutron radiation prevention boron carbide concrete according to claim 1, wherein the cement is portland cement, the strength grade is 42.5, and the specific surface area is 300-360 cm2/g, loss on ignition is less than or equal to 5.0 percent.
3. The neutron radiation prevention boron carbide concrete according to claim 1, wherein the particle size of the boron carbide is 0-3 mm, the purity is not less than 95%, the sieving rate is not less than 98%, the mud content is not more than 3.0%, the mud cake content is not more than 1.0%, and the fineness modulus is 1.9.
4. The neutron radiation prevention boron carbide concrete according to claim 1, wherein the fly ash is class II F fly ash, the fineness is less than or equal to 25.0%, the water demand ratio is less than or equal to 105%, the loss on ignition is less than or equal to 8.0%, and the sulfur trioxide content is less than or equal to 3.0%.
5. The neutron radiation prevention boron carbide concrete according to claim 1, wherein the slag powder is above S95 grade, and the specific surface area is as follows: 400-500 m2Kg, density is more than or equal to 2.8g/cm3The fluidity ratio is more than or equal to 95 percent, the ignition loss is less than or equal to 3.0 percent, the sulfur trioxide content is less than or equal to 4.0 percent, the activity index in 7 days is more than or equal to 75 percent, and the activity index in 28 days is more than or equal to 95 percent.
6. The neutron radiation prevention boron carbide concrete of claim 1, wherein the fine aggregate is natural II medium sand, the fineness modulus is 2.3-3.0, the mud content is less than or equal to 3.0%, the mud block content is less than or equal to 1.0%, the water absorption rate is less than or equal to 2%, and the bulk density is greater than or equal to 1400kg/m3Apparent density is more than or equal to 2500kg/m3The porosity is less than or equal to 44 percent;
the coarse aggregate is crushed stone which is II-class continuous graded crushed stone with the maximum grain diameter of 5-25 mm, the compact void ratio is less than or equal to 45 percent, the mud content is less than or equal to 1.0 percent, the mud block content is less than or equal to 0.2 percent, and the apparent density is more than or equal to 2600kg/m3The crushing index value is less than or equal to 20 percent, and the needle sheet content is less than or equal to 10 percent.
7. The neutron radiation prevention boron carbide concrete according to claim 1, wherein the water reducing agent is a polycarboxylic acid high-performance water reducing agent, the water reducing rate is not less than 25%, the gas content is not more than 6.0%, the bleeding rate ratio is not more than 50%, and the pressure bleeding rate ratio is not more than 90%.
8. The neutron radiation prevention boron carbide concrete according to claim 1, wherein the water parameters are satisfied, the pH value is not less than 4.5, the chloride ion is not more than 1000mg/L, the sulfate ion is not more than 2000mg/L, the insoluble matter is not more than 2000mg/L, and the soluble matter is not more than 5000 mg/L.
9. The neutron radiation prevention boron carbide concrete according to any one of claims 1 to 8, which specifically comprises the following components in parts by weight:
gel material: 700 parts of (1);
fine aggregate: 383 parts of;
coarse aggregate: 1142 parts of a carrier;
water: 175 parts of a lubricant;
water reducing agent: 7.5 parts;
the gel material comprises the following components in parts by weight:
cement: 308 parts of (A);
fly ash: 46 parts of (a);
slag powder: 86 parts of a binder;
boron carbide: 260 parts of (A).
10. The preparation method of the neutron radiation prevention boron carbide concrete is characterized by comprising the following steps:
pouring the coarse aggregate, the fine aggregate, the fly ash and the slag powder into a stirring tank in sequence;
starting the stirring tank, and stirring for a first set time;
pouring boron carbide and cement into a stirring tank in sequence;
starting the stirring tank, and stirring for a second set time;
pouring water and a water reducing agent into a stirring tank;
starting the stirring tank, and continuously stirring according to the set stirring speed and the third set time.
CN202111612402.3A 2021-12-27 2021-12-27 Neutron radiation prevention boron carbide concrete and preparation method thereof Pending CN114031353A (en)

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CN114835452A (en) * 2022-05-06 2022-08-02 上海建工建材科技集团股份有限公司 Boron-containing barite radiation-proof concrete and preparation method thereof
CN115140985A (en) * 2022-08-08 2022-10-04 华北水利水电大学 Boron carbide ultra-high performance concrete and preparation method and application thereof

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JP2008157801A (en) * 2006-12-25 2008-07-10 Fujita Corp Neutron shielding low-activation concrete and mortar
CN102219459A (en) * 2011-04-02 2011-10-19 武汉理工大学 Radiation shield concrete and preparation method thereof
CN108675711A (en) * 2018-05-11 2018-10-19 中铁二十局集团第二工程有限公司 Ready-mixed concrete construction method under high and cold alternate freezing and thawing environment

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JP2008157801A (en) * 2006-12-25 2008-07-10 Fujita Corp Neutron shielding low-activation concrete and mortar
CN102219459A (en) * 2011-04-02 2011-10-19 武汉理工大学 Radiation shield concrete and preparation method thereof
CN108675711A (en) * 2018-05-11 2018-10-19 中铁二十局集团第二工程有限公司 Ready-mixed concrete construction method under high and cold alternate freezing and thawing environment

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN114835452A (en) * 2022-05-06 2022-08-02 上海建工建材科技集团股份有限公司 Boron-containing barite radiation-proof concrete and preparation method thereof
CN115140985A (en) * 2022-08-08 2022-10-04 华北水利水电大学 Boron carbide ultra-high performance concrete and preparation method and application thereof

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