CN106978563B - A kind of Al-B4C-B neutron absorber materials and preparation method thereof - Google Patents

A kind of Al-B4C-B neutron absorber materials and preparation method thereof Download PDF

Info

Publication number
CN106978563B
CN106978563B CN201710232367.XA CN201710232367A CN106978563B CN 106978563 B CN106978563 B CN 106978563B CN 201710232367 A CN201710232367 A CN 201710232367A CN 106978563 B CN106978563 B CN 106978563B
Authority
CN
China
Prior art keywords
powder
jacket
temperature
composite material
obtains
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Active
Application number
CN201710232367.XA
Other languages
Chinese (zh)
Other versions
CN106978563A (en
Inventor
鲜亚疆
庞晓轩
张鹏程
刘鹏闯
张羽廷
王鑫
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Institute of Materials of CAEP
Original Assignee
Institute of Materials of CAEP
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Institute of Materials of CAEP filed Critical Institute of Materials of CAEP
Priority to CN201710232367.XA priority Critical patent/CN106978563B/en
Publication of CN106978563A publication Critical patent/CN106978563A/en
Application granted granted Critical
Publication of CN106978563B publication Critical patent/CN106978563B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C32/00—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ
    • C22C32/0047—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with carbides, nitrides, borides or silicides as the main non-metallic constituents
    • C22C32/0052—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with carbides, nitrides, borides or silicides as the main non-metallic constituents only carbides
    • C22C32/0057—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with carbides, nitrides, borides or silicides as the main non-metallic constituents only carbides based on B4C
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B22—CASTING; POWDER METALLURGY
    • B22F—WORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F3/00—Manufacture of workpieces or articles from metallic powder characterised by the manner of compacting or sintering; Apparatus specially adapted therefor ; Presses and furnaces
    • B22F3/02—Compacting only
    • B22F3/04—Compacting only by applying fluid pressure, e.g. by cold isostatic pressing [CIP]
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B22—CASTING; POWDER METALLURGY
    • B22F—WORKING METALLIC POWDER; MANUFACTURE OF ARTICLES FROM METALLIC POWDER; MAKING METALLIC POWDER; APPARATUS OR DEVICES SPECIALLY ADAPTED FOR METALLIC POWDER
    • B22F3/00—Manufacture of workpieces or articles from metallic powder characterised by the manner of compacting or sintering; Apparatus specially adapted therefor ; Presses and furnaces
    • B22F3/12—Both compacting and sintering
    • B22F3/14—Both compacting and sintering simultaneously
    • B22F3/15—Hot isostatic pressing
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C1/00—Making non-ferrous alloys
    • C22C1/04—Making non-ferrous alloys by powder metallurgy
    • C22C1/05—Mixtures of metal powder with non-metallic powder
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C21/00—Alloys based on aluminium

Abstract

The invention discloses a kind of Al B4C B neutron absorber materials and preparation method thereof, it is therefore intended that solve with B in aluminum-based boron carbide4The preparation difficulty of the increase of C granule contents, composite board also increases therewith, and processing performance and plasticity are deteriorated, it is difficult to it rolls, and B in aluminum-based boron carbide4C content is too low, and is unable to ensure neutron shield performance, it is difficult to ensure the problem of criticality safety.The present invention obtains the equally distributed composite material of particle dispersion, and comprehensive performance is good, has excellent anti-radiation performance, is used to have higher criticality safety when spent fuel storage rack material, and meet the needs of neutron-absorbing.

Description

A kind of Al-B4C-B neutron absorber materials and preparation method thereof
Technical field
The present invention relates to nuclear radiation protection field, especially radiation protection neutron absorber material field, specially a kind of Al- B4C-B neutron absorber materials and preparation method thereof.
Background technology
In recent years, with nuclear energy fast development and make full use of, a large amount of spentnuclear fuel also generates therewith.These spentnuclear fuels With hot and toxicity, a large amount of gamma-rays and neutron are constantly released, it may occur however that criticality accident seriously endangers the mankind Health and living environment.It is expected that after the year two thousand twenty, China will unload over thousands of ton spentnuclear fuel every year.Since not have system still complete in China Kind spentnuclear fuel reprocessing rate, the cumulant of spentnuclear fuel will quickly exceed the processing capacity of spentnuclear fuel.In future, China is in weary combustion It will also have a difficult task before sb in terms of material post-processing problem, production is needed to prepare large batch of, good quality neutron-absorbing material Material, to realize storage and transport to spentnuclear fuel.
Currently, common neutron absorber material includes boron steel, Boron-containing-PE, cadmium plate etc..Wherein, boron content mistake in boron steel It is low, it is difficult to meet shielding demand；Boron-containing-PE is brittle under radiation environment, short life；Cadmium plate is toxic, carcinogenic, and absorbs It will produce second-order activity after neutron.
In addition, aluminum-based boron carbide is also commonly used as irradiated fuel store and transport material.Aluminum-based boron carbide has in higher thermal Muon capture cross-sectional area, good corrosion resistance, good heat stability, irradiation stability are good.However, in aluminum-based boron carbide B4The preparation difficulty of the increase of C granule contents, composite board also increases therewith, and processing performance and plasticity are deteriorated, it is difficult to roll； And too low B4C content is unable to ensure neutron shield performance again, it is difficult to ensure criticality safety.
For this purpose, there is an urgent need to a kind of new materials, to solve the above problems.
Invention content
The goal of the invention of the present invention is：For with B in aluminum-based boron carbide4The increase of C granule contents, composite board Preparation difficulty also increase therewith, processing performance and plasticity are deteriorated, it is difficult to roll, and B in aluminum-based boron carbide4C content is too low, again Be unable to ensure neutron shield performance, it is difficult to ensure the problem of criticality safety, provide a kind of Al-B4C-B neutron absorber materials and its Preparation method.The present invention obtains the equally distributed composite material of particle dispersion, and comprehensive performance is good, has excellent Flouride-resistani acid phesphatase Can, it is used to have higher criticality safety when spent fuel storage rack material, and meet the needs of neutron-absorbing.
To achieve the goals above, the present invention adopts the following technical scheme that：
A kind of new A l-B4C-B neutron absorber materials are prepared using the component of following mass percent：
9.9% ~ 25% B4C, 0.1 ~ 3% boron powder, 72% ~ 90% is Al or Al alloys；
The boron powder is natural boron powder or concentration10The boron powder of B isotopes.
The aluminium alloy is 1XXX line aluminium alloys, 2XXX line aluminium alloys, 3XXX line aluminium alloys, 4XXX line aluminium alloys, 5XXX It is one or more in line aluminium alloy or 6XXX line aluminium alloys.
The grain size of the Al or Al alloys is 10 ~ 50 μm, and the grain size of the boron carbide powder is 1 ~ 30 μm, the boron powder Diameter is 0.1 ~ 20 μm.
Preferably, the mass fraction of the boron powder is 0.1 ~ 0.5%.
Preferably, the mass fraction of the boron powder is 0.5 ~ 3.0%.
The preparation method of previous materials, includes the following steps：
（1）It weighs
Each component is weighed according to the ratio, it is spare；
（2）Ball mill mixing
The powder that step 1 is weighed is added in ball mill, then ethyl alcohol is added into ball mill and is flooded to powder surface by ethyl alcohol Not yet, 2 ~ 8h of ball milling at 150r/min ~ 350r/min, obtains the first mixed powder, by the first mixed powder of gained 35 ~ 80 24 ~ 48h of heat preservation and dryness at DEG C obtains the second mixed powder；
（3）Isostatic cool pressing
Second mixed powder prepared by step 2 is fitted into mold, and is evacuated to vacuum degree and is less than 10Pa, then in 150- Under 250MPa, pressurize 10-20min obtains isostatic cool pressing green body；
（4）Jacket and high-temperature degassing
The jacket of isostatic cool pressing blank shape is made in metal welding, and a snorkel is reserved in the sealing of jacket, then Isostatic cool pressing green body prepared by step 3 removes mold, and removes the isostatic cool pressing green body after mold and be fitted into jacket, and welding is close The sealing of hole of package set, carries out high-temperature degassing, and vacuumize in 350 DEG C ~ 420 DEG C temperature ranges after jacket is hunted leak, vacuum degree dimension It holds to 10-2~10-4Pa obtains the composite material containing jacket；
（5）High-temperature process
The composite material obtained using step 4 carries out vaccum sintering process processing, and sintering temperature is 400 ~ 630 DEG C, when sintering Between be 6 ~ 28 hours, vacuum degree 10-3Pa can get the composite material pellet of consistency >=94%；
Or the composite material obtained using step 4 carries out hot isostatic pressing method processing, and temperature is 560-640 DEG C, pressure is 40 ~ 110MPa, dwell time are 5 ~ 60min, and pressure medium is argon gas, can get the composite material pellet of consistency >=99%；
（6）Post-processing
After composite material pellet removal jacket prepared by step 5, products obtained therefrom is post-processed to get Al-B4C-B Neutron absorber material.
In the step 2, the first mixed powder of gained is put into thermostatic drying chamber, at 35 ~ 80 DEG C heat preservation and dryness 24 ~ 48h obtains the second mixed powder.
In the step 3, pressure 180MPa, pressurize 15min obtain isostatic cool pressing green body.
In the step 4, the jacket of isostatic cool pressing blank shape is welded into using iron plate.
The thickness of iron plate is 1mm-3mm.
In the step 5, when carrying out hot isostatic pressing method processing, temperature is 580-620 DEG C.
In the step 5, vacuum-sintering temperature is 460 DEG C, sintering time 12h；Or the temperature of hot isostatic pressing is 600 DEG C, pressure 50MPa, pressurize 15min.
In the step 6, after products obtained therefrom angle grinder or milling machine surface polishing, hot rolling, then annealed place are carried out Aligning is to get Al-B after reason4C-B neutron-absorbing planks.
For foregoing problems, a kind of Al-B4C-B neutron absorber materials of present invention offer and preparation method thereof.Wherein, in this Sub- absorbing material according to mass fraction by 0.9% ~ 25% B4C, 0.1 ~ 3% B element, 72% ~ 90% is Al or Al alloys； And the B element in the material is with natural boron powder or concentration10Prepared by the form addition of the boron powder of B isotopes.
The mass fraction of boron powder is 0.1 ~ 0.5%, and with natural boron powder or concentration10The form of the boron powder of B isotopes is added It prepares, B is solid-solubilized in Al or Al alloys, B4C particles form clean free from admixture with the interface compared with high bond strength with Al.
The mass fraction of B element is 0.5 ~ 3.0%, and with natural boron powder or concentration10The form of the boron powder of B isotopes adds Add standby, B is solid-solubilized in Al or Al alloys, and a small amount of B is with AlB2Or simple substance form exists, B4C particles form clean free from admixture with Al With the interface compared with high bond strength.
Further, the present invention provides the preparation method of previous materials.In the present invention, component is weighed first：By mass fraction Each component is weighed respectively.Secondly, ball mill mixing：The powder that step 1 obtains is mixed, is mixed using ball mill, Analysis absolute alcohol is added until mixed powder surface is flooded, rotating speed is 150r/min ~ 350r/min, and Ball-milling Time is 2 ~ 8 Hour, obtain the first mixed powder；First mixed powder is put into thermostatic drying chamber kept the temperature at 35 ~ 80 DEG C and dry 24 ~ 48h obtains dry mixed powder, is denoted as the second mixed powder.Again, isostatic cool pressing：The second mixed powder that step 2 is obtained Body is fitted into mold, vacuumize make vacuum degree be less than 10Pa, then pressure be 150-250MPa, the condition of pressurize 10-20 minutes Green body is made in lower progress isostatic cool pressing.Again, jacket and high-temperature degassing are filled：Green body is made in the isostatic cool pressing that step 3 obtains, is torn open Except mold, iron plate is used（Thickness 1mm-3mm）Welding is prepared into the jacket of blank shape, and sealing part reserves a snorkel；It will be cold Isostatic pressing is fitted at green body in jacket, and welded seal sealing carries out high-temperature degassing, in 350 DEG C ~ 420 DEG C temperature models after leak detection It encloses and vacuumizes, vacuum degree is maintained to 10-2~10-4Pa.Again, high-temperature process：The composite material that step 4 obtains is sintered, According to vaccum sintering process, then sintering temperature is 400 ~ 630 DEG C, and sintering time is 6 ~ 28 hours, vacuum degree 10-3Pa can be obtained Obtain the composite material pellet of consistency >=94%；According to hot isostatic pressing method, then temperature is 560-640 DEG C（It is preferred that 580-620 ℃）, pressure is 40 ~ 110MPa, and the dwell time is 5 minutes ~ 60 minutes, and pressure medium is argon gas, can get consistency >=99% Composite material pellet.Finally, jacket is removed, composite material pellet is taken out, after angle grinder or milling machine surface polishing, heat can be carried out It rolls, is aligned after annealing, obtain Al-B4C-B neutron-absorbing planks.
Material of the present invention is Al-B4C-B ternary systems, the neutron absorber material can effectively shield thermal neutron, and easily In machine-shaping, welding performance is good, adapt to Nuclear Power Station's Exhausted Fuels storage densification, long life developing direction, meet weary combustion The use demand of material storage screen work material, maintains subcritical state, it is ensured that storage safety, while can also be applied to nuclear industry field Other neutron shielding fields.
10B has higher neutron absorption ability, and (n α) occurs with neutron and reacts, and SE secondary emission will not be caused dirty Dye can efficiently control reactivity in nuclear reactor, maintain subcritical state, it is ensured that criticality safety.
Due to10B has excellent neutron absorption performance, Al/B4C composite is commonly used for the storage of nuclear reactor spentnuclear fuel It deposits and transport applications, 6061Al-31wt.%B4C is a kind of neutron absorber material that nuclear power field compares favor, but due to B4C Content is up to 31%, and leading to composite material, there are bigger difficulty in preparation, for example it is difficult to densified sintering product, hot rolling is easy to out It splits, B4C particles are easy to the further extensive use that reunion etc. all constrains the composite material, in contrast, Al-20wt.%B4C is multiple The preparation difficulty of condensation material then substantially reduces, but due to B4C content is reduced to 20%, causes composite board needs to do enough Thickness could meet enough neutron-absorbing performances, but thicker plank can cause, and the spacing of fuel assembly is caused to increase, difficult To realize the high density storage of spentnuclear fuel.
On the other hand, Al-B alloys begin to be studied as solid fuel early in the sixties in last century, are not only Spentnuclear fuel wet method stores one of the candidate material in field, also has the foreground of application in military field.
This patent is designed by material composition, has developed novel Al-B4The composite material of C-B ternary systems, it is therefore an objective to Reduce B4C content reduces the densification sintering of composite board and the difficulty of hot rolling process, improves the lumber recovery of composite board, On the other hand, in order not to weaken the neutron-absorbing performance of composite material, and a small amount of B is added, to make up the B of loss4The neutron of C Absorbent properties, it is ensured that Al-B4C-B ternary systems not only have higher neutron-absorbing performance, also have lower preparation difficult Degree reduces production cost, this is also the difference and unique distinction of this patent and other aluminum-based boron carbide materials.
In conclusion the present invention innovatively proposes a kind of novel neutron absorber material Al-B4C-B ternary systems are compound Material, the composite material consistency prepared is high, has excellent neutron-absorbing performance.In addition, novel Al-B4C-B is compound Material can reduce B4C granule contents reduce the preparation difficulty of aluminum-based boron carbide, and due to being added to B, neutron shield performance It will not be impacted, it is ensured that the criticality safety during irradiated fuel store, and novel Al-B4C-B composite materials also meet The characteristics of following irradiated fuel store highly denseization, long life.
Description of the drawings
Examples of the present invention will be described by way of reference to the accompanying drawings, wherein：
Fig. 1 is the Al-B that embodiment 1 obtains4The scanning electron microscope microstructure figure of C-B neutron absorber materials
Fig. 2 is the Al-B that embodiment 2 obtains4The transmission electron microscope microstructure figure of C-B neutron absorber materials；
Fig. 3 is the Al-B that embodiment 5 obtains4The scanning electron microscope microstructure figure of C-B neutron absorber materials；
Fig. 4 is the Al-B that embodiment 6 obtains4The scanning electron microscope microstructure figure of C-B neutron absorber materials.
Specific implementation mode
All features disclosed in this specification or disclosed all methods or in the process the step of, in addition to mutually exclusive Feature and/or step other than, can combine in any way.
Any feature disclosed in this specification unless specifically stated can be equivalent or with similar purpose by other Alternative features are replaced.That is, unless specifically stated, each feature is an example in a series of equivalent or similar characteristics .
Embodiment 1
Step 1 weighs：20% B is weighed by mass fraction4C powder, 0 .5%B powder, 79.5% 5083 Al alloy powder.
Step 2 ball mill mixing：The powder that step 1 obtains is mixed, is mixed using planetary ball mill, Analysis absolute alcohol is added until mixed powder surface is flooded, rotating speed 180r/min, Ball-milling Time is 6 hours, is mixed Powder；Mixed powder is put into thermostatic drying chamber heat preservation and dry 30h at 70 DEG C, obtains dry mixed powder.
Step 3 isostatic cool pressing：The dried powder that step 2 obtains is fitted into mold, vacuumizing makes vacuum degree maintain 8Pa or so, then in pressure be 180MPa, carrying out isostatic cool pressing under conditions of pressurize 10 minutes is made green body, and green density is 83%。
Step 4 fills jacket and high-temperature degassing：The green body that step 3 is obtained removes mold, uses iron plate（Thickness 1mm）Weldering The jacket for being prepared into blank shape is connect, sealing part reserves a snorkel；Green body is fitted into jacket, welded seal sealing, inspection High-temperature degassing is carried out after leakage, is vacuumized at 405 DEG C, and vacuum degree is maintained to about 10-3Pa。
Step 5 HIP sintering：The composite material that step 4 is obtained carries out HIP sintering, temperature 600 DEG C, pressure 50MPa, the dwell time is 10 minutes, and pressure medium is argon gas, after the completion of sintering, removes jacket, takes out composite wood Expect pellet, after angle grinder or milling machine surface polishing, hot rolling can be carried out, aligned after annealing, consistency 99.9% is obtained Al-B4C-B neutron-absorbing planks.
Embodiment 2
Present embodiment is as different from Example 1：20% B is weighed by mass fraction4C powder, 1 .0%B powder, 79.0% 5083 Al alloy powder.It is other in the same manner as in Example 1.
Embodiment 3
Present embodiment is as different from Example 1：20% B is weighed by mass fraction4C powder, 1.5%B powder, 78.5% 5083 Al alloy powders.Other are in the same manner as in Example 1.
Embodiment 4
Present embodiment is unlike embodiment 1, embodiment 2, embodiment 3：The aluminium alloy be 1XXX line aluminium alloys, 2XXX line aluminium alloys, 3XXX line aluminium alloys, 4XXX line aluminium alloys or 6XXX line aluminium alloys.Other are identical as embodiment 1-3.
Embodiment 5
Step 1 weighs：20% B is weighed by mass fraction4C powder, 0 .5%B powder, 79.5% 6061 Al alloy powder.
Step 2 ball mill mixing：The powder that step 1 obtains is mixed, is mixed using planetary ball mill, Analysis absolute alcohol is added until mixed powder surface is flooded, rotating speed 185r/min, Ball-milling Time is 6.5 hours, is mixed Close powder；Mixed powder is put into thermostatic drying chamber heat preservation and dry 36h at 75 DEG C, obtains dry mixed powder.
Step 3 isostatic cool pressing：The dried powder that step 2 obtains is fitted into mold, vacuumizing makes vacuum degree maintain 10Pa or so, then in pressure be 175MPa, carrying out isostatic cool pressing under conditions of pressurize 15 minutes is made green body, and green density is 82%。
Step 4 fills jacket and high-temperature degassing：The green body that step 3 is obtained removes mold, uses iron plate（Thickness 1mm）Weldering The jacket for being prepared into blank shape is connect, sealing part reserves a snorkel；Green body is fitted into jacket, welded seal sealing, inspection High-temperature degassing is carried out after leakage, is vacuumized at 405 DEG C, and vacuum degree is maintained to about 10-3Pa。
Step 5 vacuum-sintering：The composite material that step 4 is obtained carries out vacuum-sintering, and sintering temperature is 440 DEG C, is burnt It is 16 hours to tie the time, vacuum degree 10-3Pa；After the completion of sintering, remove jacket, take out composite material pellet, with angle grinder or After milling machine surface polishing, hot rolling can be carried out, is aligned after annealing, obtain the Al-B of consistency 98%4C-B neutron absorber plates Material.
Embodiment 6
Present embodiment is as different from Example 5：20% B is weighed by mass fraction4C powder, 1.5%B powder, 78.5% 6061 Al alloy powders, vacuum-sintering temperature are 480 DEG C, and sintering time is 12 hours, vacuum degree 10-3Pa, other and embodiment 5 In it is identical.
Embodiment 7
Present embodiment is as different from Example 5：20% B is weighed by mass fraction4C powder, 2.0%B powder, 78% 6061 Al alloy powders.Vacuum-sintering temperature is 540 DEG C, and sintering time is 8 hours, vacuum degree 10-3Pa, other and embodiment 5 In it is identical.
Embodiment 8
Present embodiment is unlike embodiment 5-7：The aluminium alloy be 1XXX line aluminium alloys, 2XXX line aluminium alloys, 3XXX line aluminium alloys, 4XXX line aluminium alloys or 5XXX line aluminium alloys.Other are same as Example 6.
The invention is not limited in specific implementation modes above-mentioned.The present invention, which expands to, any in the present specification to be disclosed New feature or any new combination, and disclose any new method or process the step of or any new combination.

Claims (6)

1. a kind of Al-B4The preparation method of C-B neutron absorber materials, which is characterized in that include the following steps：
（1）It weighs
Each component is weighed by following proportioning：
9.9% ~ 25% B4C, 0.1 ~ 3% boron powder, 72% ~ 90% is Al or Al alloys；
The boron powder is natural boron powder or concentration10The boron powder of B isotopes, it is spare；
（2）Ball mill mixing
By step（1）The powder weighed is added in ball mill, then ethyl alcohol is added into ball mill and is flooded to powder surface by ethyl alcohol, 2 ~ 8h of ball milling at 150r/min ~ 350r/min, obtains the first mixed powder, by the first mixed powder of gained at 35 ~ 80 DEG C 24 ~ 48h of lower heat preservation and dryness, obtains the second mixed powder；
（3）Isostatic cool pressing
By step（2）The second mixed powder prepared is fitted into mold, and is evacuated to vacuum degree and is less than 10Pa, then in 150- Under 250MPa, pressurize 10-20min obtains isostatic cool pressing green body；
（4）Jacket and high-temperature degassing
The jacket of isostatic cool pressing blank shape is made in metal welding, and a snorkel is reserved in the sealing of jacket, then will step Suddenly（3）The isostatic cool pressing green body of preparation removes mold, and removes the isostatic cool pressing green body after mold and be fitted into jacket, welded seal The sealing of hole of jacket carries out high-temperature degassing, and is vacuumized in 350 DEG C ~ 420 DEG C temperature ranges after jacket is hunted leak, vacuum degree maintains To 10-2~10-4Pa obtains the composite material containing jacket；
（5）High-temperature process
Using step（4）Obtained composite material carries out vaccum sintering process processing, and sintering temperature is 400 ~ 630 DEG C, sintering time It it is 6 ~ 28 hours, vacuum degree is less than 10-3Pa can get the composite material pellet of consistency >=94%；
Or use step（4）Obtained composite material carries out hot isostatic pressing method processing, and temperature is 560-640 DEG C, and pressure is 40 ~ 110MPa, dwell time are 5 ~ 60min, and pressure medium is argon gas, can get the composite material pellet of consistency >=99%；
（6）Post-processing
By step（5）After the composite material pellet removal jacket of preparation, products obtained therefrom is post-processed to get Al-B4In C-B Sub- absorbing material.
2. according to the method described in claim 1, it is characterized in that, the step（2）In, the first mixed powder of gained is put into In thermostatic drying chamber, 24 ~ 48h of heat preservation and dryness at 35 ~ 80 DEG C obtains the second mixed powder.
3. according to the method described in claim 1, it is characterized in that, the step（3）In, pressure 180MPa, pressurize 15min obtains isostatic cool pressing green body.
4. according to the method described in claim 1, it is characterized in that, the step（5）In, when carrying out hot isostatic pressing method processing, Temperature is 580-620 DEG C.
5. according to the method described in claim 1, it is characterized in that, the step（5）In, vacuum-sintering temperature is 460 DEG C, is burnt The knot time is 12h；Or the temperature of hot isostatic pressing is 600 DEG C, pressure 50MPa, pressurize 15min.
6. according to the method described in claim 1, it is characterized in that, the step（6）In, by products obtained therefrom angle grinder or milling After the polishing of bed surface, aligning is to get Al-B after carrying out hot rolling, then annealed processing4C-B neutron-absorbing planks.
CN201710232367.XA 2017-04-11 2017-04-11 A kind of Al-B4C-B neutron absorber materials and preparation method thereof Active CN106978563B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201710232367.XA CN106978563B (en) 2017-04-11 2017-04-11 A kind of Al-B4C-B neutron absorber materials and preparation method thereof

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201710232367.XA CN106978563B (en) 2017-04-11 2017-04-11 A kind of Al-B4C-B neutron absorber materials and preparation method thereof

Publications (2)

Publication Number Publication Date
CN106978563A CN106978563A (en) 2017-07-25
CN106978563B true CN106978563B (en) 2018-10-02

Family

ID=59344293

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201710232367.XA Active CN106978563B (en) 2017-04-11 2017-04-11 A kind of Al-B4C-B neutron absorber materials and preparation method thereof

Country Status (1)

Country Link
CN (1) CN106978563B (en)

Families Citing this family (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN109913680A (en) * 2017-12-13 2019-06-21 北京有色金属研究总院 A kind of neutron shield aluminum matrix composite and preparation method thereof
CN108588500A (en) * 2018-05-11 2018-09-28 中国工程物理研究院材料研究所 A kind of quick semisolid warm area forming method of neutron absorber material
CN109500387B (en) * 2018-10-09 2021-02-09 镇江华核装备有限公司 Structural function integration B4CAl neutron absorbing composite
CN111118329B (en) * 2020-01-19 2021-11-23 江苏大学 Preparation method and device of high-toughness high-neutron absorption aluminum-based composite material
CN111489796B (en) * 2020-03-24 2022-06-10 上海交通大学 Method, system and medium for calculating neutron shielding performance of material
CN113458394B (en) * 2021-05-20 2023-04-07 中国工程物理研究院材料研究所 Homogeneous boron carbide/aluminum composite material with high boron carbide content and preparation method thereof

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105499583A (en) * 2015-12-16 2016-04-20 北京有色金属研究总院 Preparation method for B4C/Al composite material boards

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105499583A (en) * 2015-12-16 2016-04-20 北京有色金属研究总院 Preparation method for B4C/Al composite material boards

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
"用于反应堆乏燃料贮存和运输的B4C/Al复合材料研究进展";鲜亚疆等;《材料导报Ａ：综述篇》;20150228;第29卷(第2期);第45-48页 *

Also Published As

Publication number Publication date
CN106978563A (en) 2017-07-25

Similar Documents

Publication Publication Date Title
CN106978563B (en) A kind of Al-B4C-B neutron absorber materials and preparation method thereof
CN105200274B (en) A kind of preparation method of neutron absorber material
CN108335760B (en) Preparation method of high-uranium-loading-capacity dispersed fuel pellet
Yang et al. UO2–UN composites with enhanced uranium density and thermal conductivity
CN109852850A (en) A kind of preparation method of structure-function integration neutron absorber material
CN106756164A (en) A kind of thermal structure function integration B4The preparation method of C/Al neutron absorber materials
CN111205067B (en) Glass-ceramic material for cooperative protection of neutrons and gamma rays and preparation method thereof
CN109797308A (en) A kind of new oxide dispersion-strengtherning neutron absorber material
CN109797309A (en) A kind of structure-function integration neutron absorber material High-Temperature Strengthening method
CN107180654A (en) A kind of MAX phase ceramics matrix disperse pellet nuclear fuel and its preparation method and purposes
CN105671373A (en) Preparing method for neutron absorption plate with high B4C content
WO2019085593A1 (en) Fuel pellet manufacturing method and fuel pellet
Kim et al. Synthesis and characteristics of ternary Be–Ti–V beryllide pebbles as advanced neutron multipliers
CN110527887A (en) A kind of shielding neutron and the boron tungsten aluminium composite material of gamma ray and preparation method thereof
WO2019114315A1 (en) Fuel pellet doped with boron carbide and fabrication method therefor
JP2002536542A (en) Zirconium and niobium alloys containing erbium as consumable neutron poison, method for preparing the same, and parts containing the alloys
WO2020150976A1 (en) Coated fuel particle, inert matrix dispersed fuel pellet and integrated fuel rod, and fabrication methods therefor
CN111326265B (en) Uranium dioxide-carbide composite fuel pellet and preparation method thereof
US2967141A (en) Neutronic reactor fuel element
CN102432295A (en) Ceramic substrate neutron absorption ball and preparation method thereof
CN115058268B (en) Composite structure fuel and preparation method thereof
CN109868467B (en) Preparation method of anti-radiation reinforced composite coating on surface of aluminum alloy
USH897H (en) Boron-copper neutron absorbing material and method of preparation
KR102229519B1 (en) METHOD FOR MANUFACTURING URANIUM TARGET TO BE SOLUBLE IN BASIC SOLUTION AND METHOD FOR EXTRACTING RADIOACTIVE Mo-99 USING THE SAME
US20230258419A1 (en) Low-cost engineered particles for thermal energy transfer or storage

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant