CN109545415A - A kind of radiation protection material - Google Patents
A kind of radiation protection material Download PDFInfo
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- CN109545415A CN109545415A CN201811338101.4A CN201811338101A CN109545415A CN 109545415 A CN109545415 A CN 109545415A CN 201811338101 A CN201811338101 A CN 201811338101A CN 109545415 A CN109545415 A CN 109545415A
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- neutron
- radiation protection
- boron carbide
- protection material
- absorbing material
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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
- G21F1/10—Organic substances; Dispersions in organic carriers
- G21F1/103—Dispersions in organic carriers
- G21F1/106—Dispersions in organic carriers metallic dispersions
Abstract
The invention discloses a kind of radiation protection materials, including matrix, curing agent, neutron-absorbing material, densifier, the mass ratio of described matrix and curing agent, densifier is 1:0.1 ~ 0.5:1 ~ 2, and the quality of neutron-absorbing material accounts for the 0.5 ~ 1.5% of gross mass, and the neutron-absorbing material is combined for 5 ~ 30% modified boron carbides with 65 ~ 95% ultra-high molecular weight polyethylenes by mass ratio；The present invention is compound with ultra-high molecular weight polyethylene by that will be modified boron carbide, in conjunction with ultra-high molecular weight polyethylene degraded neutron, boron carbide absorbs the advantages of neutron, and it acts synergistically with a certain amount of matrix, curing agent, densifier, it is prepared for that a kind of system viscosity is low, is suitable for being poured various profile shapes, and protium content is high, it can be effectively by neutron degradation, while there is the new neutron radiation-screening protective materials of excellent mechanical performance and neutron shield performance.
Description
Technical field
The present invention relates to the material shielded to the spentnuclear fuel that nuclear power station generates more particularly to a kind of radiation protection materials
Material.
Background technique
It is planned according to China's nuclear power Long-and Medium-term Development, arrive the year two thousand twenty, nuclear power operation installed capacity is striven for reaching 40,000,000 kw,
While nuclear power projects construction, low level waste disposal field in synchronized construction, with adapt to nuclear power developing it is ever-increasing in
The processing of cool waste needs；Nuclear Power Station's Exhausted Fuels have hot, it is necessary to consider Radiation Protection, especially in
Sub- ray is just particularly important its protection, neutron since neutron ray has the characteristics that energy is big, penetration capacity is strong
The application of shielding material has obtained great concern, is mainly used for nuclear reactor in nuclear power station and vulnerable to neutron irradiation pollution
The protection at the positions such as building, device and equipment.
With nuclear technology and industrial expansion, it has been found that boron carbide neutron absorption ability with higher, this be because
Contain for it10B,10B is one of 2 kinds of stable isotopes of natural boron istope, and thermal neutron absorption cross section is 3837 barns, is led to
Cross reaction10After B (n, α) 7Li absorbs neutron, the He and Li of releasing are "dead", and the compound of the boron made --- boron carbide becomes
Safer shielding material,10B abundance 18.8% in natural boron, it is very strong to the absorption of neutron, but have to the absorption of fast neutron
Limit.
Currently used neutron absorber has boron carbide ceramics plate, boron carbide-aluminium composite material plate, boron carbide powder mixing
Colloid is cold-pressed into template and boron carbide powder painting mode etc., boron carbide composite material, the boron carbide ceramics material of aluminium base
Expect that Weldability is still to be tested, while the carbonization boron content adulterated is few, while being restricted in terms of thickness requirement, while such material
That there are heat aging properties is poor for material, and processability is poor, and viscosity is bad, is not suitable for that casting, mechanical performance is bad, shield effectiveness is poor
Situations such as.
Summary of the invention
It is heat-resisting old to overcome that in response to the problems existing in the prior art, the purpose of the present invention is to provide a kind of radiation protection materials
The problems such as changing that performance is poor, and processability is poor, and viscosity is bad, being not suitable for casting, at the same material have excellent mechanical performance and
Neutron shield performance.
To achieve the above object, the technical solution adopted by the present invention is that:
A kind of radiation protection material, including matrix, curing agent, neutron-absorbing material, densifier, described matrix and curing agent,
The mass ratio of densifier is 1:0.1 ~ 0.5:1 ~ 2, and the quality of neutron-absorbing material accounts for the 0.5 ~ 1.5% of gross mass, the neutron
Absorbent is combined for 5 ~ 30% modified boron carbides with 65 ~ 95% ultra-high molecular weight polyethylenes by mass ratio.
It is compound with ultra-high molecular weight polyethylene that the present invention will be modified boron carbide, in conjunction in ultra-high molecular weight polyethylene slowing down
The advantages of son, boron carbide absorbs neutron, and act synergistically with a certain amount of matrix, curing agent, densifier, it is prepared for one kind
System viscosity is low, protium content is high, can be effectively by neutron degradation, while having excellent mechanical performance and neutron shield
The new neutron radiation-screening protective materials of performance.
Preferably, the modified boron carbide is that silane coupling agent KH570 hydrolysis processing boron carbide in ethanol solution is made,
Silane coupling agent KH570 dosage be boron carbide quality 1 ~ 5%, the ethanol solution mass fraction be 70%, the boron carbide with
The solid-to-liquid ratio of ethyl alcohol is (5-30) mg:100ml.
KH570 silane coupling agent has preferable coupled action to boron carbide, is properly added KH570 and enhances boron carbide and surpass
Binding force between High molecular weight polyethylene can be effectively improved matrix and granular boundary, reduce hole between two-phase, improve material
Toughness is expected, so that material, when being impacted by external load, bearing load has touching section to increase, so that reinforcing material impact is strong
Degree；Coupling agent excessively can form extra physical absorption layer in carbonization boron surface simultaneously, be filled in boron carbide and super high molecular weight
Between polyethylene, lubricating action is played, reduces material impact intensity.
The present invention also provides the neutron-absorbing materials the preparation method is as follows: being in mass ratio added to modified boron carbide super
In High molecular weight polyethylene, ball milling is hot-forming.
Boron carbide/ultra-high molecular weight polyethylene composite material is prepared by hydro-forming, after temperature increases, polymer segment
The mobility of freedom of movement, ultra-high molecular weight polyethylene improves, and is conducive to the discharge of gas and the reduction of defect, makes material more
Closely knit, bearing load effective cross-section increases, and impact strength improves.
Preferably, the ball milling condition of the preparation method of the neutron-absorbing material are as follows: ball milling speed is 220 ~ 250r/
Min, Ball-milling Time are 0.5 ~ 1h.
Preferably, the hot-forming condition of the preparation method of the neutron-absorbing material are as follows: pressure 20MPa, hot pressing
Temperature is 160 ~ 200 DEG C, keeps the temperature 2h.
Preferably, described matrix is bisphenol f type epoxy resin.
Bisphenol f type epoxy resin be reacted under acidic catalyst by phenol and formaldehyde generate Bisphenol F, then with epoxychloropropane
Polycondensation reaction is made, it is suitable with bisphenol A type epoxy resin performance, and reaction speed is slightly slow, and viscosity only has bisphenol A type epoxy resin
1/3, be more suitable for neutron shielding material resin Composition.
Preferably, any one of the curing agent in triethylene tetramine, tetraethylenepentamine and isophorone diamine,
The amine hardener is conducive to system viscosity, reaction speed, the balance of heat resistance, and effectively increases protium content.
Preferably, the densifier is aluminium hydroxide, and the partial size of aluminium hydroxide is 100 ~ 1000 mesh, and aluminium hydroxide exists
It can be used simultaneously as density adjuster and fire retardant in radiation protection material, the partial size and dosage limited according to the present invention can make
System viscosity, density, fire protecting performance reach best.
The present invention also provides a kind of preparation methods of radiation protection material, the method is as follows: by the mass ratio
Matrix, neutron-absorbing material, densifier, which are added to, to be stirred under vacuum in cylinder, is vacuumized, is stirred 30min, stop stirring, opening is put
To normal pressure the curing agent of the mass ratio is added, closure is stirred under vacuum cylinder, vacuumizes, and stirring is opened, after stirring 10min in empty valve
Stop stirring, emptying to normal pressure, discharging, normal temperature cure.
The method dispersed using vacuum can avoid in material preparation process because high speed dispersion generates a large amount of bubble, suppression
The generation in drilling hole improves the mechanical performance and neutron shield performance of material.
Preferably, the preparation method of a kind of radiation protection material, the vacuum degree are 0.001 ~ 0.01Pa.
Compared with prior art, the beneficial effects of the present invention are:
(1) present invention will modified boron carbide and ultra-high molecular weight polyethylene it is compound, in conjunction with ultra-high molecular weight polyethylene degraded neutron,
Boron carbide absorbs the advantages of neutron, and acts synergistically with a certain amount of matrix, curing agent, densifier, is prepared for a kind of body
It is that viscosity is low, protium content is high, can be effectively by neutron degradation, while there is excellent mechanical performance and neutron shield
The new neutron radiation-screening protective materials of energy.
(2) present invention has preferable coupled action to boron carbide by KH570 silane coupling agent, is properly added KH570 increasing
Strong binding force between boron carbide and ultra-high molecular weight polyethylene, can be effectively improved matrix and granular boundary, reduce two-phase
Between hole, improve toughness of material and impact strength.
(3) present invention by optimization matrix, curing agent, neutron-absorbing material, densifier proportion be prepared for compared with
Low system viscosity is suitable for being poured various profile shapes, while can also be used as coating and being applied, and hydrogen with higher member
Cellulose content, can be effectively by neutron degradation, while material has the radiation of excellent mechanical performance and neutron shield performance anti-
Protective material.
Detailed description of the invention
Fig. 1 is the neutron shield the performance test results figure of radiation protection material made from the embodiment of the present invention 1 ~ 5.
Fig. 2 is the scanning electron microscope phenogram of radiation protection material made from embodiment 1.
Fig. 3 is shielding properties of the radiation protection material made from the embodiment of the present invention 1 and embodiment 12 ~ 16 to thermal neutron
Test result figure.
Fig. 4 is embodiment 1, the impact strength and bending strength test result of the obtained radiation protection material of embodiment 17 ~ 18
Figure.
Fig. 5 is the impact strength and bending strength test result figure of the obtained radiation protection material of embodiment 1 ~ 5.
Fig. 6 is embodiment 1, embodiment 21, the impact strength of radiation protection material is made for embodiment 22 and bending strength is surveyed
Test result figure.
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；Unless stated otherwise, the present invention uses reagent, method and apparatus is the art conventional reagents, method
And equipment.
Embodiment 1
A kind of radiation protection material, including bisphenol f type epoxy resin matrix, tetraethylenepentamine curing agent, neutron-absorbing material, partial size
For the aluminium hydroxide densifier of 300 mesh, the mass ratio of described matrix and curing agent, densifier is 1:0.2:1.6, in
The quality of sub- absorbent accounts for the 1% of gross mass, and the neutron-absorbing material is 15% modified boron carbide and 85% supra polymer by mass ratio
Weight northylen is combined.
The neutron-absorbing material the preparation method is as follows:
(1) 0.6g silane coupling agent KH570 is taken, it is to stir in 70% ethanol solution with 300r/min that 100ml mass fraction, which is added,
20min adds 20g boron carbide, disperses 15min with 300W ultrasonic echography, and be heated to 80 DEG C of insulated and stirred 1h, is cooled to
Filter residue is filtered to obtain after room temperature, filter residue is placed in drying box, is dried at 80 DEG C to constant weight, is obtained modified boron carbide.
(2) modified boron carbide 20% made from step (1) is weighed in mass ratio to be added in 80% ultra-high molecular weight polyethylene,
With 220 ~ 250r/min ball milling 0.5h, pressure 20MPa, hot pressing temperature is 180 DEG C, keeps the temperature the hot-forming obtained neutron-absorbing of 2h
Agent.
The preparation method of the radiation protection material, the method is as follows: by the matrix of the mass ratio, neutron-absorbing material, close
Degree dose, which is added to, to be stirred under vacuum in cylinder, is evacuated to 0.001Pa, is stirred 30min, stops stirring, opens blow valve to normal
The curing agent of the mass ratio is added in pressure, and closure is stirred under vacuum cylinder, is evacuated to 0.001Pa, stirring is opened, after stirring 10min
Stop stirring, emptying to normal pressure, discharging, normal temperature cure.
Embodiment 2
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material
Quality account for the 0.5% of gross mass.
Remaining is all the same with embodiment 1.
Embodiment 3
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material
Quality account for the 0.7% of gross mass.
Remaining is all the same with embodiment 1.
Embodiment 4
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material
Quality account for the 1.3% of gross mass.
Remaining is all the same with embodiment 1.
Embodiment 5
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material
Quality account for the 1.5% of gross mass.
Remaining is all the same with embodiment 1.
Embodiment 6
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, described matrix and curing agent,
The mass ratio of densifier is 1:0.1:1.
Remaining is all the same with embodiment 1.
Embodiment 7
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, described matrix and curing agent,
The mass ratio of densifier is 1:0.5:2.
Remaining is all the same with embodiment 1.
Embodiment 8
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the curing agent is three second
Alkene tetramine.
Remaining is all the same with embodiment 1.
Embodiment 9
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the curing agent is different Buddhist
That ketone diamines.
Remaining is all the same with embodiment 1.
Embodiment 10
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the aluminium hydroxide density
The partial size of dose is 100 mesh.
Remaining is all the same with embodiment 1.
Embodiment 11
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the aluminium hydroxide density
The partial size of dose is 1000 mesh.
Remaining is all the same with embodiment 1.
Embodiment 12
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material by
Mass ratio is that 5% modified boron carbide is combined with 95% ultra-high molecular weight polyethylene.
Remaining is all the same with embodiment 1.
Embodiment 13
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material by
Mass ratio is that 10% modified boron carbide is combined with 90% ultra-high molecular weight polyethylene.
Remaining is all the same with embodiment 1.
Embodiment 14
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material by
Mass ratio is that 20% modified boron carbide is combined with 80% ultra-high molecular weight polyethylene.
Remaining is all the same with embodiment 1.
Embodiment 15
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material by
Mass ratio is that 25% modified boron carbide is combined with 75% ultra-high molecular weight polyethylene.
Remaining is all the same with embodiment 1.
Embodiment 16
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material by
Mass ratio is that 30% modified boron carbide is combined with 70% ultra-high molecular weight polyethylene.
Remaining is all the same with embodiment 1.
Embodiment 17
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the modified boron carbide
Silane coupling agent KH570 dosage is the 1% of boron carbide quality in preparation method.
Remaining is all the same with embodiment 1.
Embodiment 18
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the modified boron carbide
Silane coupling agent KH570 dosage is the 5% of boron carbide quality in preparation method.
Remaining is all the same with embodiment 1.
Embodiment 19
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the modified boron carbide
The solid-to-liquid ratio of boron carbide described in preparation method and ethyl alcohol is 5mg:100ml.
Remaining is all the same with embodiment 1.
Embodiment 20
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the modified boron carbide
The solid-to-liquid ratio of boron carbide described in preparation method and ethyl alcohol is 30mg:100ml.
Remaining is all the same with embodiment 1.
Embodiment 21
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material system
The hot-forming condition of Preparation Method are as follows: pressure 20MPa, hot pressing temperature are 160 DEG C, keep the temperature 2h.
Embodiment 22
The present embodiment provides a kind of radiation protection materials, compared with Example 1, the difference is that, the neutron-absorbing material system
The hot-forming condition of Preparation Method are as follows: pressure 20MPa, hot pressing temperature are 200 DEG C, keep the temperature 2h.
Comparative example 1
This comparative example provides a kind of radiation protection material, compared with Example 1, the difference is that, the neutron-absorbing material is
Boron carbide.
Application examples 1
Radiation protection material made from embodiment 1 ~ 5 is made with a thickness of 1cm template, carries out neutron shield performance test respectively,
As a result as shown in Figure 1 (ratio that neutron shield capacity calculation value is neutron counting after being put into template and before being put into).
As seen from Figure 1, increasing with embodiment neutron-absorbing agent content, the neutron shield energy of radiation protection material material
Power rises rapidly: continuing growing the content of neutron-absorbing material, the trend that neutron shield ability rises slows down；Comprehensively consider, for
With a thickness of the neutron shielding material of 1 cm, when neutron-absorbing material additive amount is 1% in embodiment 1, radiation protection material template is just
90% or more neutron can be shielded, the effect of preferable shielding neutron can be played.
Radiation protection material made from Example 1 is scanned electron microscope characterization, as a result as shown in Fig. 2, by scheming
Middle result it is found that densifier and modified boron carbide neutron-absorbing material disperse in system it is relatively uniform while several in system
Hole is not present, density is larger.
Application examples 2
Radiation protection material made from embodiment 1 and embodiment 12 ~ 16 is made and carries out thermal neutron with a thickness of 0.5 ~ 2cm template
Attenuation coefficient research, test use americium-plating neutron source, each sample test 200s；In composite board neutron-absorbing material
From 5 ~ 30%, attenuation coefficient ∑ is calculate by the following formula content, whereinI。The quantity of detector is directly entered for neutron per second, I is warp
Crossing the sample quantity per second into detector, X is thickness of sample, I=I。e-∑。X, as a result as shown in figure 3, can by result in figure
Know, attenuation coefficient is larger when sample strip is relatively thin, and with the increase of thickness of sample, attenuation coefficient is gradually reduced；This show energy compared with
Low thermal neutron almost all when thickness of sample is relatively thin is predominantly absorbed, and shield effectiveness is good；The higher fast neutron of energy with
The increase of thickness of sample collides, energy is absorbed after being reduced, and thermal neutron with the increase of modified carbonization boron content
Transmitance, which reduces, shows that the increase of thickness enhances the shield effectiveness of neutron；The sample strip of same thickness, with modified boron carbide
The increase of content, attenuation coefficient increase with it, and the transmitance of thermal neutron reduces therewith, this shows that modified carbonization boron content increases,
It is stronger to the absorption of neutron；With the increase of material thickness and the increase for the boron content that is carbonized, the shield effectiveness of neutron is added
By force, therefore can be according to neutron source the case where, the reasonable additive amount and optimal template thickness for selecting modified boron carbide have
Help avoid wasting.
Application examples 3
Radiation protection material made from embodiment 1 and comparative example 1 is made and carries out density and various mechanics with a thickness of the template of 1cm
Performance detection, the results are shown in Table 1.
It is by upper table result it is found that compound with ultra-high molecular weight polyethylene by modified boron carbide, it is anti-to effectively improve radiation
The density and mechanical property of protective material illustrate that the present invention is reasonable by each component compatibility, and synergistic effect is between each other to make to make
The radiation protection material various aspects of performance obtained reaches best.
Application examples 4
The impact strength and bending strength of testing example 1, the obtained radiation protection material of embodiment 17 ~ 18, as a result such as Fig. 4 institute
Show, You Tuzhong it is found that in embodiment 1 silane coupling agent additive amount be carbonized boron content 3% or so when, radiation protection material
Impact strength and bending strength reach maximum value, and 1 performance of embodiment is best, and changes silane coupling agent additive amount, and performance is equal
It can reduce.
Application examples 5
The impact strength and bending strength of the obtained radiation protection material of testing example 1 ~ 5, as a result as shown in figure 5, by can in figure
Know, reduces afterwards as neutron-absorbing agent content increase radiation protection material impact strength first increases, ultra-high molecular weight polyethylene is
High-toughness material, and being modified boron carbide particles is inorganic rigid material in irregular shape, the two is compounded to form composite material and draws
The impact strength of radiation protection material can be improved by entering base；When continuing growing with modified carbonization boron content, particle is difficult to disperse, and produces
It is raw to reunite, cause stress to concentrate, bulky grain plays the part of defect role in the base, and the brittleness for resulting in radiation protection material increases,
Reduce material impact intensity；With the increase of modified carbonization boron content, bending strength is increased slightly, but amplitude of variation is little,
And 1 neutron-absorbing agent content of embodiment be 15% when be made radiation protection material impact strength and bending strength performance it is best.
Application examples 6
The impact strength and bending strength of radiation protection material is made in testing example 1, embodiment 21, embodiment 22, as a result such as
Shown in Fig. 6, You Tuzhong is it is found that impact strength is increased with hot pressing temperature before 180 DEG C and improved, and variation is little after 180 DEG C；
Bending strength value reduces afterwards as temperature raising first increases, but entire change very little；This is because preparing radiation under lower temperature
Have more porous in the matrix of protective materials, and hole is obviously less in 180 DEG C of matrixes for preparing radiation protection material, temperature liter
Gao Hou, polymer segment freedom of movement, Flow Properties of Uhmwpe improve, and are conducive to the discharge of gas and subtracting for defect
It is few, keep radiation protection material obtained more closely knit, bearing load effective cross-section increases, and impact strength improves；Radiation protection material
Expect that bending strength is relatively small to flaw sensitivity, variation is little, and 1 performance of embodiment is best.
The above, only of the invention illustrates embodiment, not to the present invention in any form with substantial limitation,
It should be pointed out that for those skilled in the art, under the premise of not departing from the method for the present invention, that makes several changes
It also should be regarded as protection scope of the present invention into supplement；All those skilled in the art, do not depart from spirit of that invention and
In the case where range, using the equivalent variations of a little change, modification and differentiation that disclosed above technology contents are made, it is
Equivalent embodiment of the invention；Meanwhile any equivalent variations that all substantial technologicals according to the present invention do above-described embodiment
Change, modification and differentiation, still fall within protection scope of the present invention.
Claims (10)
1. a kind of radiation protection material, which is characterized in that including matrix, curing agent, neutron-absorbing material, densifier is described
Matrix and curing agent, densifier mass ratio be 1:0.1 ~ 0.5:1 ~ 2, the quality of neutron-absorbing material account for gross mass 0.5 ~
1.5%, the neutron-absorbing material is combined for 5 ~ 30% modified boron carbides with 65 ~ 95% ultra-high molecular weight polyethylenes by mass ratio.
2. a kind of radiation protection material according to claim 1, which is characterized in that the modified boron carbide is silane coupled
Agent KH570 hydrolysis handles boron carbide in ethanol solution and is made, and silane coupling agent KH570 dosage is the 1 ~ 5% of boron carbide quality,
The ethanol solution mass fraction is 70%, and the solid-to-liquid ratio of the boron carbide and ethyl alcohol is (5-30) mg:100ml.
3. a kind of radiation protection material according to claim 1, which is characterized in that the preparation method of the neutron-absorbing material
It is as follows: modified boron carbide to be added in ultra-high molecular weight polyethylene in mass ratio, ball milling is hot-forming.
4. a kind of radiation protection material according to claim 3, which is characterized in that the ball milling condition are as follows: ball milling speed
For 220 ~ 250r/min, Ball-milling Time is 0.5 ~ 1h.
5. a kind of radiation protection material according to claim 3, which is characterized in that the hot-forming condition are as follows: pressure
For 20MPa, hot pressing temperature is 160 ~ 200 DEG C, keeps the temperature 2h.
6. a kind of radiation protection material according to claim 1, which is characterized in that described matrix is bisphenol F type epoxy tree
Rouge.
7. a kind of radiation protection material according to claim 1, which is characterized in that the curing agent is selected from triethylene four
Any one in amine, tetraethylenepentamine and isophorone diamine.
8. a kind of radiation protection material according to claim 1, which is characterized in that the densifier is hydroxide
Aluminium, the partial size of aluminium hydroxide are 100 ~ 1000 mesh.
9. a kind of preparation method of radiation protection material described in claim 1, which is characterized in that method is as follows: by the matter
Matrix, neutron-absorbing material, the densifier of amount ratio, which are added to, to be stirred under vacuum in cylinder, is vacuumized, is stirred 30min, stops stirring,
Blow valve is opened to normal pressure, the curing agent of the mass ratio is added, closure is stirred under vacuum cylinder, vacuumizes, and opens stirring, stirring
Stop stirring, emptying to normal pressure, discharging, normal temperature cure after 10min.
10. a kind of preparation method of radiation protection material according to claim 9, which is characterized in that the vacuum degree is
0.001~0.01Pa。
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN110767340A (en) * | 2019-10-10 | 2020-02-07 | 中广核研究院有限公司 | Novel composite shielding material of tungsten boron crosslinked polyethylene with high tungsten content |
| CN112356534A (en) * | 2020-11-09 | 2021-02-12 | 哈尔滨工业大学 | Radiation protection composite material and preparation method thereof |
| CN113306239A (en) * | 2021-04-25 | 2021-08-27 | 郑州大学 | Ultrahigh molecular weight polyethylene fiber/boron nitride composite material for neutron radiation protection and preparation method thereof |
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| CN112356534B (en) * | 2020-11-09 | 2022-12-20 | 哈尔滨工业大学 | Radiation protection composite material and preparation method thereof |
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