CN110415851A - A kind of cement base neutron shielding material and preparation method thereof - Google Patents
A kind of cement base neutron shielding material and preparation method thereof Download PDFInfo
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- CN110415851A CN110415851A CN201910716570.3A CN201910716570A CN110415851A CN 110415851 A CN110415851 A CN 110415851A CN 201910716570 A CN201910716570 A CN 201910716570A CN 110415851 A CN110415851 A CN 110415851A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/04—Concretes; Other hydraulic hardening materials
- G21F1/042—Concretes combined with other materials dispersed in the carrier
- G21F1/045—Concretes combined with other materials dispersed in the carrier with organic substances
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/04—Concretes; Other hydraulic hardening materials
- G21F1/042—Concretes combined with other materials dispersed in the carrier
- G21F1/047—Concretes combined with other materials dispersed in the carrier with metals
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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
The invention discloses a kind of cement base neutron shielding material, including basis material and function aggregate, the weight ratio of described matrix material and the function aggregate is 1:0.45~0.55；Described matrix material includes the component of following parts by weight: the weight of 100 parts of complex cement, 5~15 parts of polymer, 0.8 part of polycarboxylate water-reducer and carbon fiber and the carbon fiber is the 3% of described matrix material weight；The function aggregate includes the component of following parts by weight: 46~58 parts of gradation graphite particle and shielding absorb 13.6~14.3 parts of powder.The cement base neutron shielding material improves the neutron shield performance of conventional cement base neutron shielding material, mechanical property and compatibility.The invention also discloses a kind of preparation methods of cement base neutron shielding material.
Description
Technical field
The invention belongs to building material technical field, it is related to the screen to the design of nuclear power station shielded layer and radioactivity spentnuclear fuel
Cover processing, and in particular to a kind of cement base neutron shielding material and preparation method thereof.
Background technique
Neutron ray usually goes out a kind of high-energy particle flow caused by the fission of autothermal reactor center or nuclear fusion, although it
In electroneutral, but penetration power is very strong, and propagation distance is farther, and radiation injury is higher.With the fast development of nuclear energy, the production of nuke rubbish
It measures increasing, the control of the quality of Nuclear Safety shielded layer and the storage of nuke rubbish processing aspect is just particularly important.
Conventional cement sill is cheap, there is certain shield effectiveness to neutron and gamma ray, but shield effectiveness
It is not high.Boracic class neutron-absorbing material and high density heavy aggregate are directly added into cement-based material presently mainly to improve material
Neutron shield effect often result in cement base because the difference of material component density is big and the deferred action of boracic class spike
The delamination degree of neutron shielding material is big, and working performance is very poor, and mechanical strength is low.In addition, neutron and cement base shielding material are mutual
When effect, the atomic collision with material internal makes that thermal energy can be generated inside cement matrix, and the excessively high one side of temperature can directly make water
The intracorporal free water evaporation of mud base, to influence neutron shield performance；The raising of another aspect temperature can make to produce inside cement matrix
Raw expansion, there is the danger in production crack.
Summary of the invention
It is an object of the invention to overcome above-mentioned technical deficiency, a kind of cement base neutron shielding material, the cement base are proposed
Neutron shielding material improves the neutron shield performance of conventional cement base neutron shielding material, mechanical property and compatibility；This
The purpose of invention another aspect is, proposes a kind of preparation method of cement base neutron shielding material, and the preparation method is simple, former
Expect that source is wide.
To reach above-mentioned technical purpose, technical solution of the present invention provides a kind of cement base neutron shielding material, including base
The weight ratio of body material and function aggregate, described matrix material and the function aggregate is 1:0.45~0.55；Described matrix material
Material includes the component of following parts by weight: 100 parts of complex cement, 5~15 parts of polymer, 0.8 part of polycarboxylate water-reducer and carbon fiber
Dimension and the weight of the carbon fiber are the 3% of described matrix material weight；The function aggregate includes the component of following parts by weight:
46~58 parts of gradation graphite particle and shielding absorb 13.6~14.3 parts of powder.
Technical solution of the present invention additionally provides a kind of preparation method of cement base neutron shielding material, including walks as follows
It is rapid:
S1, it stocks up by weight；
S2, polymer and water are uniformly mixed, obtain lotion, complex cement, carbon fiber are added in Xiang Suoshu lotion and gathers
Carboxylic acid water reducer is uniformly mixed, obtains gel basis material；Shielding is absorbed into powder and PVA powder adhesion agent is uniformly mixed,
Gradation graphite particle after adding drying is uniformly mixed, obtains function aggregate；
S3, described matrix material and the function aggregate are uniformly mixed according to mass ratio for 1:0.45~0.55, are obtained
Finished product.
Compared with prior art, the beneficial effect comprise that
1, cement base neutron shielding material provided by the invention is by being added complex cement, before can not only improving single cement
Phase intensity deficiency and later strength retraction, moreover it is possible to the setting time for adjusting basis material, be added additionally by basis material
Polymer, polycarboxylate water-reducer and carbon fiber are modified basis material, the diminishing and filming function of these types of substance, not only
The cohesive force and thixotropy of complex cement slurry can be improved, moreover it is possible to improve the cohesiveness of basis material；
2, make gradation graphite particle in basis material by the way that gradation graphite particle is added in function aggregate provided by the invention
In be uniformly distributed, also improve shielding and absorb the uniformity that is distributed in basis material of powder, and be unlikely to make basis material and
Excessive delamination occurs for function aggregate, can not only improve the working performance of basis material, also improves shielding and absorbs powder
To the uniform pickup effect of neutron ray；In addition, on the one hand graphite particle and carbon fiber have neutron reflection absorption, another party
There is good thermal conductivity in face, can effectively scatter and disappear cement in cement base neutron shielding material as skeleton and thermal energy transmission channel
Heat inside sill improves the use temperature of cement-based material to reduce scattering and disappearing for cement-based material internal moisture
Range；
3, the preparation method of cement base neutron shielding material provided in the present invention, preparation method is simple, and raw material sources are wide,
It is suitable for industrialized production.
Specific embodiment
In order to make the objectives, technical solutions, and advantages of the present invention clearer, with reference to embodiments, to the present invention
It is further elaborated.It should be appreciated that the specific embodiments described herein are merely illustrative of the present invention, it is not used to
Limit the present invention.
The embodiment provides a kind of cement base neutron shielding material, including basis material and function aggregate, bases
The weight ratio of body material and function aggregate is 1:0.45~0.55, and wherein basis material includes the component of following parts by weight: compound
The weight of 100 parts of cement, 5~15 parts of polymer, 0.8 part of polycarboxylate water-reducer and carbon fiber and carbon fiber is basis material
The 3% of weight；Function aggregate includes the component of following parts by weight: 46~58 parts of gradation graphite particle, shielding absorb powder 13.6
~14.3 parts.
In some preferred embodiments of the invention, the weight ratio of basis material and function aggregate is 1:0.5.
In some preferred embodiments of the invention, complex cement is 42.5 cement of CA-50 aluminate cement and PO
It is compound, and the mass ratio of 42.5 cement of CA-50 aluminate cement and PO is 10~20:90~80；It is highly preferred that CA-50 aluminium
The mass ratio of 42.5 cement of acid salt cement and PO is 15:85.
In the present invention, CA-50 aluminate cement selects 45um to tail over percentage for 19.2%, presetting period 32min, eventually
The solidifying time is 98min, and 28d compression strength is 59.5MPa, and 28d flexural strength is the cement of 7.0Mpa；42.5 cement selection of P.O
It is 3.0% that 45um, which tails over percentage, presetting period 182min, and final setting time 245min, 28d compression strength is 52.6MPa,
28d flexural strength is the cement of 8.0MPa.
In some preferred embodiments of the invention, polymer is aqueous epoxy resins H-223A and epoxy hardener H-
The mixture of 223B, and the mass ratio of aqueous epoxy resins H-223A and epoxy hardener H-223B are 1:2.
In the present invention, the aqueous epoxy resins H-223A that uses for light thick liquid, 25 DEG C of viscosity are 8500~
12500mPaS, non-volatile content content are 96~98%, and epoxide equivalent is 195~255；The epoxy hardener H- of use
223B is yellowish thick liquid, and 25 DEG C of viscosity are 2560~6300mPaS, and non-volatile content content is 51~53%, epoxy
Equivalent is 185~193.
In the present invention, the length of the carbon fiber used is 1~1.8mm, carbon content >=98%, stretch modulus be 220~
260GPa, tensile strength are 3.1~3.6GPa, and elongation is 1.3~1.4%.
In the present invention, polycarboxylate water-reducer uses SD-F series polycarboxylate water-reducer, water-reducing rate 30%.
In some preferred embodiments of the invention, water is also contained in basis material, and water-cement ratio is 0.45.
In some preferred embodiments of the invention, function aggregate includes the component of following parts by weight: gradation graphite
50 parts of grain, shielding absorb 14 parts of powder.
In some preferred embodiments of the invention, it is B that shielding, which absorbs powder,4The mixing of C powder and barite powder
Object, and B4The mass ratio of C powder and barite powder is 2.7~3.5:7.3~6.5；It is highly preferred that B4C powder and blanc fixe
The mass ratio of body is 3:7.
In the present invention, it is 98.6~99.4% that carbon content is fixed in gradation graphite particle, and gradation partial size is 0.8~3.0mm,
Cylindrical compress strength is 29.5~30.6MPa, and room temperature thermal coefficient is 280~330W/ (mk), bulk density 1.74g/cm3, ash
Divide≤0.1%；In some preferred embodiments of the invention, gradation graphite particle is sub-elected into D1=0.8~2mm and D2=2
Two gradations of~3mm, and D1And D2Mass ratio be 4:6.
In the present invention, B4C powder is a kind of black fluffy powder of almost spherical, and average particle size is in 1~10um, density
2.52g/cm3, purity >=98.5%；Barite powder is a kind of grey white facing, BaSO4Content >=95%, average grain diameter be 10~
20um, density 4.30g/cm3, the hydrotrope≤0.1%.
In the present invention, PVA (polyvinyl alcohol) powder adhesion agent is also contained in function aggregate, the molecular formula of PVA is
(C2H4O)n, appearance is yellowish powdered high molecular polymer, and chemical stability is good；To PVA powder adhesion agent in the present invention
Amount do not limit particularly, those skilled in the art can adjust the dosage of PVA powder adhesion agent according to the actual situation.This
Function aggregate is using a kind of shell-core structure function aggregate made of PVA packing technology in invention, and core is by gradation graphite group
At shell is by B4C powder and barite powder form.
The embodiments of the present invention also provide a kind of preparation methods of cement base neutron shielding material, include the following steps:
(1) it stocks up by weight；
(2) polymer and water are uniformly mixed, obtain lotion, complex cement, carbon fiber and polycarboxylic acids are added into lotion
Water-reducing agent is uniformly mixed, obtains with the preferable gel basis material of mobility；Shielding is absorbed into powder and PVA powder glues
It ties agent to be uniformly mixed, the gradation graphite particle after adding drying is uniformly mixed, obtains function aggregate；
(3) it is that 1:0.45~0.55 is uniformly mixed according to mass ratio by basis material and function aggregate, obtains finished product.
Neutron shield alpha ray shield is generally divided into two processes, is that high-energy neutron and heavy element (Pb and Ba etc.) are sent out first
Raw inelastic scattering makes its energy largely decay, then utilizes elastic scattering by the energy attenuation of neutron by light elements such as carbon, hydrogen
To thermal energy range；The absorption stage of followed by slow thermal neutron (is mostly mainly to contain by the biggish material in neutron absorption cross-section
Boron compound) by neutron absorption.Containing a large amount of hydrocarbon to neutron energy attenuation in basis material of the invention
With significant effect, shields absorption function powder and be actually made of one layer of shell-core structure, shell B4C and barite powder,
Under the action of PVA binder with the gradation graphite tight adhesion as core, wherein barite powder as introduce heavy element
Effectively with fast neutron inelastic scattering can occur for ingredient, so that its energy is largely decayed, B4C powder is mainly used to slow thermal neutron
Absorption, and nuclear graphite has the characteristic of good slowing down and reflection to neutron.Neutron and nuclear graphite can occur when acting on reflection from
And slowing down absorption process occurs with shell powder again.The design of shell-core structure function aggregate, so that neutron ray is from single
Slowing down-absorption process is changed into the process that slowing down-absorption-reflection-slowing down absorbs, under the shielding material of same thickness indirectly
The action time for enhancing shielding material and neutron and distance, substantially improve the shielding assimilation effect of neutron ray.
In order to make the objectives, technical solutions, and advantages of the present invention clearer, below in conjunction with specific embodiment, to this
Invention is further elaborated.It should be appreciated that the specific embodiments described herein are merely illustrative of the present invention, not
For limiting the present invention.
Experimental method in the present invention is unless otherwise specified conventional method.Experimental material used in the present invention is such as
It is that market is commercially available without specified otherwise.
Embodiment 1:
The embodiment of the present invention 1 provides the basis material in a kind of cement base neutron shielding material, the basis material packet
Include the component of following parts by weight: 90 parts of CA-50 aluminate cement, 10 parts of 42.5 cement of PO, 5 parts of polymer (H- in polymer
The mass ratio of 223A and H-223B is 1:2), the weight of 0.8 part of polycarboxylate water-reducer and carbon fiber and carbon fiber be matrix material
Expect the 3% of parts by weight, water-cement ratio 0.45.
The basis material is prepared with the following method: first being mixed epoxy resin H-223A and epoxy hardener H-223B and is added
Enter water to stir to form lotion, CA-50 aluminate cement, 42.5 portland cement of PO and carbon fiber is then added and sufficiently stirs
It mixes, polycarboxylate water-reducer is slowly added into whipping process, ultimately form the gel basis material of good fluidity.
Embodiment 2~9:
Prepare the basis material of embodiment 2~9 according to the method for embodiment 1, raw material and preparation method with embodiment 1,
Difference is that the proportion of raw material is different, and the proportion of Examples 1 to 9 basis material is as shown in table 1.
The proportion (parts by weight) of 1 Examples 1 to 9 basis material of table
The physical and mechanical property of basis material obtained is as shown in table 2 in Examples 1 to 9.
The physical and mechanical property of 2 Examples 1 to 9 basis material of table
As can be seen from Table 2, the presetting period of basis material, final setting time was in 132~162min all in 67~85min.
And practical is merely 160~190min with the presetting period of 42.5 cement of PO, final setting time is 240~260min；It is simple to use
The presetting period of CA-50 aluminate cement is 30~40min, and final setting time is 100~110min.In comparison, Compound Water
The presetting period of mud system increases, and is conducive to cement-based material and pours, paves, smoothing out, receiving the operating times such as light, and final set
The reduction of time is conducive to accelerate construction progress the maintenance of the demoulding with test specimen.Often contain certain bleed and slow setting in polymer
Ingredient has certain extension to act on the setting time of matrix, slightly improves to the shrinking percentage of material.The complete film of polymer is imitated
The formation answered reinforces the filling capacity of Behavior of Hardened Cement Paste, advantageously reduces the porosity of Behavior of Hardened Cement Paste, therefore the polymer of moderate dosage
(10%) be conducive to improve resistance to compression and the flexural strength of basis material.From the point of view of backfin ratio, the polymer (10%) of moderate dosage
The flexibility of complex cement slurry can be increased, therefore the backfin of basis material is than being presented increase tendency.From the point of view of comprehensively considering, implement
Setting time, shrinking percentage and its mechanical property of example 5 are better than other groups.
Embodiment 10:
The basis material selected in embodiment 5 matches material as the matrix of function aggregate, and function aggregate includes following weight
Measure the component of part: (particle size range of gradation graphite particle is 0.8~3mm, and D to 50 parts of gradation graphite particle1(0.8-2mm) and D2
The mass ratio of (2mm-3mm) is 4:6), B414 parts of (B of mixture of C powder and barite powder4C powder and barite powder
Mass ratio is 7:3) and PVA powder adhesion agent, and the dosage of PVA powder adhesion agent is the 14% of function aggregate weight.
Function aggregate is prepared using packing technology: being first dried for standby gradation graphite particle, then by blanc fixe and B4C
Powder be mixed, and be added PVA powder adhesion agent stirring 10min after, be added drying gradation graphite quickly stir 5min~
Drying is taken out after 8min to get function aggregate is arrived.
Function aggregate obtained is uniformly mixed with the basis material in embodiment 5 according to mass ratio for 1:0.5, is obtained into
Product.
Comparative example 1:
This example prepares cement base neutron shielding material using method same as in Example 10, and difference is, in this example not
Add gradation graphite particle.
Comparative example 2:
This example prepares cement base neutron shielding material using method same as in Example 10, and difference is, in this example with
Graded broken stone (particle size range of graded broken stone particle is 0.85~3.35mm) substitution gradation graphite.
Comparative example 3:
This example prepares cement base neutron shielding material using method same as in Example 10, and difference is, in this example with
Gradation haydite (particle size range of gradation haydite particles is 0.85~3.35mm) substitution gradation graphite.
Comparative example 4:
This example prepares cement base neutron shielding material using method same as in Example 10, and difference is, function aggregate
It is prepared using blending technique: by gradation graphite particle, barite powder, B4C powder and PVA powder adhesion agent are directly stirred
Uniformly to get arrive function aggregate.
The proportion of cement base neutron shielding material in embodiment 10 and comparative example 1~4 is specifically shown in Table 3.
The different cement base neutron shielding material proportion composition tables of table 3
The mechanical property of cement base neutron shielding material obtained, wherein resistance to compression in testing example 10 and comparative example 1~4
The size of intensity test piece is 100mm × 100mm × 100mm, and the standard curing phase of test specimen is 28d；The specification of flexural strength test specimen
For 40mm × 40mm × 160mm, the standard curing age of test specimen is 28d.The Determination of conductive coefficients specimen size of test specimen be 100 ×
100 × 30mm conserves 28d under laboratory standard curing condition and takes out, is then placed in the baking oven of (105 ± 5) DEG C and dries
It is then that surface rubbing is whole to mass conservation, with the thermal coefficient of specific thermal conductivity factor instrument measurement test specimen.Dependence test result
It is shown in Table 4.
4 physical and mechanical property test result of table
The neutron shield performance of cement base neutron shielding material obtained in testing example 10 and comparative example 1~4, uses
Neutron source is the source 241Am-Be, and test equipment model LB123/6411 neutron equivalent instrument, energy section is thermal neutron energy
To 18MeV.Test shielding test specimen is dimensioned to diameter and isWith a thickness of the disc-shaped structure of 30mm, and lock screen
The front end face of test specimen and the spacing of neutron source are covered in 100cm.Shielding test specimen is penetrated with neutron transmission rate T1/T0 to characterize neutron
Ratio, wherein T1 is the intensity value that neutron penetrates shield, and T0 is the intensity value that neutron penetrates air (not set shielding material),
10keV (intermediate neutron) and 1MeV (fast neutron) energy irradiation shield is used in test process respectively, test result is shown in Table 5.
5 neutron shield performance test of table
It can be concluded that, not plus when gradation graphite particle, shielding is directly absorbed into powder from 4 test result of table and is distributed to matrix
Meeting in material is so that the delamination degree of matrix increases.Three seed nucleus aggregates are substantially reduced by packing technology processing delamination degree, directly outer
It adds and into powder the delamination degree of comparative example 4 is increased, mechanical strength embodiment 10 compared with thermal coefficient all decreases.Stone
There is certain hydrophobic effect for the opposite rubble of ink and haydite, bleeding rate slightly increases with respect to rubble, since haydite itself absorbs water
Rate is larger, and the bleeding rate of test specimen is maximum.Delamination degree is big, and bleeding rate conference directly results in the working performance and mechanics of cement-based material
Poor performance, therefore the working performance as bony nodule material of haydite is worst, and graphite and rubble are not much different；Compare nuclear graphite and
The material of core rubble, nuclear graphite preparation decreases compared to mechanical strength for core rubble, but still resistance to compression value can reach 50MPa
More than, the use of core crushed stone material can be substituted completely under normal circumstances.In addition nuclear graphite addition so that material thermally conductive system
Number highest is conducive to scattering and disappearing for shield test specimen internal heat, improves the use temperature range of material.
From 5 test result of table, it can be concluded that, in intermediate neutron area when 10keV, the neutron transmission rate of coated nuclear graphite is most
Low is 0.186, and the neutron transmission rate of directly blending type nuclear graphite is 0.453, and the material than other coated nuclear structures will
Height, the reason is that shielding absorbs powder, in the uneven distribution of matrix to directly result in neutron shield assimilation effect poor.In fast neutron energy
When area 1MeV, the neutron transmission coefficient of coated nuclear graphite is 0.372, and the neutron transmission coefficient of directly blending type nuclear graphite is unexpectedly
Up to 0.632, the reason is that neutron energy gets higher the penetrance of material when improving, shielding absorbs the inhomogeneities of powder to neutron
The influence of transmission coefficient is higher, therefore coated aggregate is more preferable compared to blending type aggregate confrontation high energy region neutron effect.Compare three
The speciality of seed nucleus, graphite have preferable neutron reflection effect, and rubble as commonly use cement-based material aggregate, haydite it is more
The transmitance that pore structure directly results in neutron ray is got higher, therefore the compactness of matrix and the speciality of aggregate are to neutron alpha ray shield
It influences very big.
In conclusion the present invention replaces conventional cement sill graded broken stone aggregate in workability using coated nuclear graphite
Excellent effect is obtained in energy, mechanical strength, the thermal conductivity of material and neutron transmission rate, is solved in conventional cement sill
The problem of sub- shielding properties and mechanical property poor compatibility, and the use temperature range of cement-based material is improved, improve screen
Cover the durability of body.
The above described specific embodiments of the present invention are not intended to limit the scope of the present invention..Any basis
Any other various changes and modifications that technical concept of the invention is made should be included in the guarantor of the claims in the present invention
It protects in range.
Claims (10)
1. a kind of cement base neutron shielding material, which is characterized in that including basis material and function aggregate, described matrix material and
The weight ratio of the function aggregate is 1:0.45~0.55；Described matrix material includes the component of following parts by weight: complex cement
The weight of 100 parts, 5~15 parts of polymer, 0.8 part of polycarboxylate water-reducer and carbon fiber and the carbon fiber is described matrix
The 3% of material weight；The function aggregate includes the component of following parts by weight: 46~58 parts of gradation graphite particle and shielding absorb
13.6~14.3 parts of powder.
2. cement base neutron shielding material according to claim 1, which is characterized in that the complex cement is CA-50 aluminium
42.5 cementitious composite of acid salt cement and PO, and the mass ratio of 42.5 cement of CA-50 aluminate cement and PO is 10~20:
90~80.
3. cement base neutron shielding material according to claim 1, which is characterized in that the polymer is water-base epoxy tree
The mixture of rouge H-223A and epoxy hardener H-223B, and the matter of aqueous epoxy resins H-223A and epoxy hardener H-223B
Amount is than being 1:2.
4. cement base neutron shielding material according to claim 3, which is characterized in that the aqueous epoxy resins H-223A
For light thick liquid, 25 DEG C of viscosity are 8500~12500mPaS, and non-volatile content content is 96~98%, epoxide equivalent
It is 195~255；The epoxy hardener H-223B is yellowish thick liquid, and 25 DEG C of viscosity are 2560~6300mPaS,
Non-volatile content content is 51~53%, and epoxide equivalent is 185~193.
5. cement base neutron shielding material according to claim 1, which is characterized in that the length of the carbon fiber be 1~
1.8mm, carbon content >=98%, stretch modulus be 220~260GPa, tensile strength be 3.1~3.6GPa, elongation be 1.3~
1.4%.
6. cement base neutron shielding material according to claim 1, which is characterized in that the polycarboxylate water-reducer uses
SD-F series polycarboxylate water-reducer, water-reducing rate 30%.
7. cement base neutron shielding material according to claim 1, which is characterized in that it is B that the shielding, which absorbs powder,4C powder
The mixture of body and barite powder, and B4The mass ratio of C powder and barite powder is 2.7~3.5:7.3~6.5.
8. cement base neutron shielding material according to claim 1, which is characterized in that the partial size of the gradation graphite particle
For 0.8~3.0mm, graphite particle is sub-elected into D1=0.8~2mm and D2Two gradations of=2~3mm, and D1And D2Mass ratio
For 4:6.
9. cement base neutron shielding material according to claim 1, which is characterized in that also contain in described matrix material
Water, water-cement ratio 0.45；Also contain the agent of PVA powder adhesion in the function aggregate.
10. a kind of preparation method of cement base neutron shielding material as described in any one of claims 1 to 9, which is characterized in that
Include the following steps:
S1, it stocks up by weight；
S2, polymer and water are uniformly mixed, obtain lotion, complex cement, carbon fiber and polycarboxylic acids is added in Xiang Suoshu lotion
Water-reducing agent is uniformly mixed, obtains gel basis material；Shielding is absorbed into powder and PVA powder adhesion agent is uniformly mixed, then plus
Gradation graphite particle after entering drying is uniformly mixed, obtains function aggregate；
S3, described matrix material and the function aggregate are uniformly mixed according to mass ratio for 1:0.45~0.55, obtain finished product.
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN111943612A (en) * | 2020-08-13 | 2020-11-17 | 中国核动力研究设计院 | Irradiation-resistant high-temperature-resistant fast neutron shielding material and preparation method thereof |
| CN115159900A (en) * | 2022-04-21 | 2022-10-11 | 湖北工业大学 | Preparation method of anti-radiation and anti-impact concrete |
| CN115321902A (en) * | 2022-08-01 | 2022-11-11 | 河北中耐新材料科技有限公司 | Anti-cracking radiation-proof concrete for preventing neutron radiation and preparation method thereof |
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