CN105200274B - A kind of preparation method of neutron absorber material - Google Patents
A kind of preparation method of neutron absorber material Download PDFInfo
- Publication number
- CN105200274B CN105200274B CN201510701250.2A CN201510701250A CN105200274B CN 105200274 B CN105200274 B CN 105200274B CN 201510701250 A CN201510701250 A CN 201510701250A CN 105200274 B CN105200274 B CN 105200274B
- Authority
- CN
- China
- Prior art keywords
- neutron
- boron carbide
- neutron absorber
- dried
- absorber material
- 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
Links
Abstract
A kind of preparation method of neutron absorber material, it is related to a kind of neutron absorber material and preparation method thereof.Can not be while composite neutron shield performance be ensured the present invention is to solve existing spentnuclear fuel shielding material, the problem of plasticity of composite can be improved again.A kind of neutron absorber material is made up by volume fraction of 10%~20% boron carbide, 1%~2% neutron-absorbing material and 78%~89% aluminum or aluminum alloy.Method：First, weigh；2nd, dry；3rd, ball mill mixing；4th, cold compaction embryo, hot pressed sintering.Neutron absorber material shielding properties produced by the present invention is high, and plasticity is good, it is easy to machine-shaping, disclosure satisfy that irradiated fuel store densification, the demand of long life, is preferable spent fuel storage rack material.The neutron absorber material of the present invention is used for nuclear industry neutron shielding field.
Description
Technical field
The present invention relates to a kind of neutron absorber material and preparation method thereof.
Background technology
Spentnuclear fuel can be become after nuclear fuel use, can be to week if dealing with improperly with very high neutron irradiation effect
Collarette border produces serious radiation pollution.With the fast development of nuclear industry, increasing nuclear power station all comes into operation in succession,
The generation of substantial amounts of spentnuclear fuel is also led to, due to limited and reactor service life the extension of storage space, nuclear industry
Spentnuclear fuel highly denseization, the challenge of long life storage are faced with, therefore higher use is proposed to spent fuel storage rack and is wanted
Ask, i.e., neutron absorption capability is strong, can meet the requirement that spentnuclear fuel is highly dense, store for a long time.Therefore there is outstanding neutron to inhale for exploitation
The material of receipts ability is to solve the problems, such as the maximally effective side of following irradiated fuel store Critical Control as spent fuel storage rack material
Method.
Conventional neutron shielding material has aluminum-boron alloy, boron steel, Boron-containing-PE and B4C/Al composites etc..Aluminium boron is closed
Gold and boron steel are because its boron content is limited, it is impossible to meet the requirement of spentnuclear fuel high density storage；Boron-containing-PE is due to matrix
For polymer, therefore mechanical property is general, while easily occurring aging embrittlement, causes its service life short.B4C/Al composite woods
Material is due to its low-density, good mechanical property, while can pass through process adjustments B4C content absorbs the energy of thermal neutron to improve
Power, becomes outstanding thermal neutron shielding material.Two kinds of the most frequently used spent fuel storage rack materials, i.e. BORAL in the world
It is B with METAMIC4C/Al composites.BORAL is the boron carbide powder and aluminium powder that will be mixed, and is put into welded seal good
Aluminium alloy box, it is aluminium sheet that levels, which are made, by the technique of hot rolling, and intermediate layer is mixed uniformly boron carbide powder and aluminium powder
The characteristics of sheet material, BORAL is that amount containing boron carbide is very high, can reach 65%, but shortcoming is because its mixed powder is not through burning
Knot, consistency is low, and plasticity is poor, while the phenomenons such as foaming easily occur in use.METAMIC uses powder metallurgical technique,
Aluminium powder and boron carbide powder are mixed, B is prepared into using techniques such as isostatic cool pressing, vacuum-sintering and extruding4C/Al composites, its
Amount containing boron carbide is high (45wt%) without BORAL, while preparation technology is complicated, it is high to equipment requirement.
The country is in recent years to B4C/Al composites have started numerous studies.Patent No. CN102392148A, invention name
Using mixed powder, cold pressing base and sintering process system referred to as in " a kind of preparation method of aluminum-based boron carbide neutron absorption composite material "
For the B of different content boron carbide amount4C/Al composites.
In Patent No. CN102280156A, entitled " a kind of preparation method of aluminum-based boron carbide neutron absorption board "
By the way of ball milling, the aluminium powder after oxidation, boron carbide powder, titanium valve, silica flour and boric acid crystal are mixed, using powder metallurgy and
B is made in the mode of hot extrusion4C/Al composite boards.But composite elongation percentage is low, only 1.8%, it is not easy to secondary add
Work is molded.
Patent No. CN102094132A, entitled " B4In C-Al composite material and preparation method thereofs ", using mixed powder, cold
Compacting base, vacuum-sintering and the technique of multiple hot rolling are prepared for containing B4The B of C amounts 5%~35%4C-Al composites, inventive result
Show, when carbonization Boron contents are less, when only 15%, composite has outstanding plasticity, and elongation percentage is up to 10%, but with carbon
Change the increase of Boron contents, plasticity declines substantially, and when carbonization Boron contents reach 30%, the elongation percentage of composite is less than 2%, also
It is to say, with the increase of carbonization Boron contents, the neutron shield performance rise of composite, but plasticity declines, and is unfavorable for material
Hot-working.
Patent No. CN102110484B, entitled " B is used in a kind of spentnuclear fuel storing4The system of C-Al neutron absorber plates
It is same that the B containing 10wt%~65wt% is prepared for using mixed powder, cold pressing base and sintering process in Preparation Method "4C-Al composite woods
Material, and be loaded into welded seal in aluminum alloy frame and carry out hot rolling again, B is finally made4C-Al neutron absorber plates.Equally exist
Above mentioned problem, i.e., high carbonization Boron contents cause the plasticity of composite drastically to decline, after hot rolling containing 35% it is compound
Material elongation percentage only has 4.1%, while consistency only has 96.8%.
Research more than is it can be found that B4C/Al composites are due to its outstanding neutron-absorbing performance, for weary combustion
Material shielding material has boundless application potential, also quite varied to this research both at home and abroad, but the weary combustion that faces the future
The characteristics of material storage highly denseization, long life, improve B4C content, that is, the neutron shield performance of composite is improved, for
B4C/Al composites are the only way which must be passed.But excessive boron carbide will certainly cause the plasticity of material to decline, and be unfavorable for being combined
The machine-shaping of material.When the Boron contents that are carbonized are more than 30%, the situation that this plasticity declines becomes particularly evident, while material
Consistency can also decline.And neutron shield performance can not be effectively ensured in too low carbonization Boron contents.Therefore how to ensure compound
While material neutron shield performance, the plasticity for improving composite is B4C/Al composites are used as spent fuel storage rack material
The problem of material development must be solved.
The content of the invention
It can not ensure the same of composite neutron shield performance the present invention is to solve existing spentnuclear fuel shielding material
When, the problem of plasticity of composite can be improved again, and a kind of neutron absorber material and preparation method thereof is provided.
A kind of neutron absorber material of the present invention is by volume fraction by 10%~20% boron carbide, 1%~2% neutron-absorbing material
It is made with 78%~89% alumina-bearing material；The boron carbide is the boron carbide particles that particle diameter is 17.5 μm or the carbon that particle diameter is 5 μm
Change boron particles；Described alumina-bearing material is aluminum or aluminum alloy.
A kind of preparation method of neutron absorber material of the present invention is to carry out according to the following steps：
First, 10%~20% boron carbide, 1%~2% neutron-absorbing material and 78%~89% are weighed by volume fraction and contains aluminium
Material；The boron carbide is the boron carbide particles that particle diameter is 17.5 μm or the boron carbide particles that particle diameter is 5 μm；
2nd, 10%~20% boron carbide, 1%~2% neutron-absorbing material and 78%~89% weighed step one contains aluminium
Material dries 24h~36h in temperature is 35 DEG C~50 DEG C of drying box respectively, obtains dried boron carbide, dried
Neutron-absorbing material and dried alumina-bearing material；
3rd, dried boron carbide, dried neutron-absorbing material and the dried alumina-bearing material obtained step 2
Mixing, then ball milling 0.5h~2h under conditions of rotating speed is 250r/min~350r/min, obtains mixed powder；By mixed powder
Body dries 24h~36h in temperature is 35 DEG C~50 DEG C of drying box, obtains dry powder；
4th, the powder for the drying for obtaining step 3 is fitted into mould, cold under conditions of pressure is 10MPa~30MPa
Idiosome is pressed into, is then put into together with mould in hot-pressed sintering furnace, be 600 DEG C~700 DEG C in hot pressing temperature is with pressure
Hot pressed sintering 2h~3h under conditions of 80MPa~120MPa, after furnace cooling, the demoulding obtains neutron absorber material.
The beneficial effects of the invention are as follows：
The neutron absorber material consistency of the present invention is high, because carbonization Boron contents are 10%~20% or so, not only acts as
Preferable enhancing effect, while the plasticity of aluminium alloy can be played, the plasticity of composite is preferable, it is easy to machine-shaping；Together
When due to the addition of the element particle in high neutron absorption section in neutron absorber material, improve absorption of the composite to neutron
Ability；The neutron absorber material prepared, with excellent mechanical property, elongation percentage is far more than equal both at home and abroad up to 8%
The B of carbonization Boron contents4C/Al composites, while having outstanding neutron-absorbing performance, are calculated, Gd volume fractions using MCNP
For 1% neutron absorber material only 2mm thickness just can shield more than 99% thermal neutron, disclosure satisfy that China at present so that future,
Irradiated fuel store highly denseization, the demand of long life.
Brief description of the drawings
Fig. 1 is the stress strain curve figure for the neutron absorber material that embodiment one is obtained；
The B that Fig. 2 is embodiment one is obtained under the conditions of Am-Be neutron sources neutron absorber material, embodiment two is obtained4C/
The B that Al composites and embodiment three are obtained4The shielding properties correlation curve of C/Al composites；Wherein 1 is that embodiment one is obtained
The neutron absorber material arrived, 2 be the B that embodiment two is obtained4C/Al composites, 3 be the B that embodiment three is obtained4C/Al composite woods
Material.
Embodiment
Embodiment one：A kind of neutron absorber material of present embodiment is by volume fraction by 10%~20% carbonization
Boron, 1%~2% neutron-absorbing material and 78%~89% alumina-bearing material are made；The boron carbide is the carbonization that particle diameter is 17.5 μm
Boron particles or the boron carbide particles that particle diameter is 5 μm；Described alumina-bearing material is aluminum or aluminum alloy.
The neutron absorber material consistency of present embodiment is high, because carbonization Boron contents are 10%~20% or so, not only
Preferable enhancing effect is served, while the plasticity of aluminium alloy can be played, the plasticity of composite is preferable, it is easy to be processed into
Type；Simultaneously because with the addition of the element particle in high neutron absorption section in neutron absorber material, composite is improved to neutron
Absorbability；The neutron absorber material prepared, with excellent mechanical property, elongation percentage is far more than the country up to 8%
The B of outer equal carbonization Boron contents4C/Al composites, while having outstanding neutron-absorbing performance, are calculated, Gd bodies using MCNP
Fraction for 1% neutron absorber material only 2mm thickness just can shield more than 99% thermal neutron, disclosure satisfy that China at present or even
Future, irradiated fuel store highly denseization, the demand of long life.
Embodiment two：Present embodiment from unlike embodiment one：Neutron absorber material presses volume
Fraction is made up of 14%~16% boron carbide, 1% neutron-absorbing material and 83%~85% alumina-bearing material.Other and specific embodiment party
Formula one is identical.
Embodiment three：Present embodiment from unlike embodiment one or two：Neutron absorber material is pressed
Volume fraction is made up of 15% boron carbide, 1% neutron-absorbing material and 84% alumina-bearing material.Other and embodiment one or two
It is identical.
Embodiment four：Unlike one of present embodiment and embodiment one to three：The neutron is inhaled
Receipts agent is Gd, Cd, Sm, Eu, Gd compound, Cd compounds, Sm compounds or Eu compounds.Other with embodiment one to
One of three is identical.
Embodiment five：Unlike one of present embodiment and embodiment one to four：The aluminium alloy
For 1xxx line aluminium alloys, 2xxx line aluminium alloys, 3xxx line aluminium alloys, 4xxx line aluminium alloys, 5xxx line aluminium alloys or 6xxx systems aluminium
Alloy.Other are identical with one of embodiment one to four.
Embodiment six：A kind of preparation method of neutron absorber material of present embodiment is to carry out according to the following steps：
First, 10%~20% boron carbide, 1%~2% neutron-absorbing material and 78%~89% are weighed by volume fraction and contains aluminium
Material；The boron carbide is the boron carbide particles that particle diameter is 17.5 μm or the boron carbide particles that particle diameter is 5 μm；Described contains aluminium
Expect for aluminum or aluminum alloy；
2nd, 10%~20% boron carbide, 1%~2% neutron-absorbing material and 78%~89% weighed step one contains aluminium
Material dries 24h~36h in temperature is 35 DEG C~50 DEG C of drying box respectively, obtains dried boron carbide, dried
Neutron-absorbing material and dried alumina-bearing material；
3rd, dried boron carbide, dried neutron-absorbing material and the dried alumina-bearing material obtained step 2
Mixing, then ball milling 0.5h~2h under conditions of rotating speed is 250r/min~350r/min, obtains mixed powder；By mixed powder
Body dries 24h~36h in temperature is 35 DEG C~50 DEG C of drying box, obtains dry powder；
4th, the powder for the drying for obtaining step 3 is fitted into mould, cold under conditions of pressure is 10MPa~30MPa
Idiosome is pressed into, is then put into together with mould in hot-pressed sintering furnace, be 600 DEG C~700 DEG C in hot pressing temperature is with pressure
Hot pressed sintering 2h~3h under conditions of 80MPa~120MPa, after furnace cooling, the demoulding obtains neutron absorber material.
The neutron absorber material consistency of present embodiment is high, because carbonization Boron contents are 10%~20% or so, not only
Preferable enhancing effect is served, while the plasticity of aluminium alloy can be played, the plasticity of composite is preferable, it is easy to be processed into
Type；Simultaneously because with the addition of the element particle in high neutron absorption section in neutron absorber material, composite is improved to neutron
Absorbability；The neutron absorber material prepared, with excellent mechanical property, elongation percentage is far more than the country up to 8%
The B of outer equal carbonization Boron contents4C/Al composites, while having outstanding neutron-absorbing performance, are calculated, Gd bodies using MCNP
Fraction for 1% neutron absorber material only 2mm thickness just can shield more than 99% thermal neutron, disclosure satisfy that China at present or even
Future, irradiated fuel store highly denseization, the demand of long life.
Embodiment seven：Present embodiment from unlike embodiment six：Volume fraction is pressed in step one
Weigh 10%~14% boron carbide, 1% neutron-absorbing material and 85%~89% alumina-bearing material.Other and the phase of embodiment six
Together.
Embodiment eight：Present embodiment from unlike embodiment six or seven：Volume is pressed in step one
Fraction weighs 15%~19% boron carbide, 1% neutron-absorbing material and 80%~84% alumina-bearing material.Other and embodiment
Six or seven is identical.
Embodiment nine：Unlike one of present embodiment and embodiment six to eight：Pressed in step one
Volume fraction weighs 20% boron carbide, 1% neutron-absorbing material and 79% alumina-bearing material.Other and embodiment six to eight it
One is identical.
Embodiment ten：Unlike one of present embodiment and embodiment six to nine：Pressed in step one
Volume fraction weighs 10%~14% boron carbide, 2% neutron-absorbing material and 84%~88% alumina-bearing material.Other and specific implementation
One of mode six to nine is identical.
Embodiment 11：Unlike one of present embodiment and embodiment six to ten：In step one
15%~19% boron carbide, 2% neutron-absorbing material and 79%~83% alumina-bearing material are weighed by volume fraction.Other and specific reality
Apply one of mode six to ten identical.
Embodiment 12：Present embodiment from unlike embodiment six to one of 11：Step one
In weigh 20% boron carbide, 2% neutron-absorbing material and 78% alumina-bearing material by volume fraction.Other with embodiment six to
One of 11 is identical.
Embodiment 13：Present embodiment from unlike embodiment six to one of 12：Step one
Described in neutron-absorbing material be Gd, Cd, Sm, Eu, Gd compound, Cd compounds, Sm compounds or Eu compounds.Other with it is specific
Embodiment six to one of 12 is identical.
Embodiment 14：Present embodiment from unlike embodiment six to one of 13：Step one
Described in aluminium alloy be that 1xxx line aluminium alloys, 2xxx line aluminium alloys, 3xxx line aluminium alloys, 4xxx line aluminium alloys, 5xxx systems aluminium are closed
Gold or 6xxx line aluminium alloys.Other are identical with embodiment six to one of 13.
Embodiment 15：Present embodiment from unlike embodiment six to one of 14：Step 2
In dry 24h in temperature is 40 DEG C of drying box.Other are identical with embodiment six to one of 14.
Embodiment 16：Present embodiment from unlike embodiment six to one of 15：Step 3
In rotating speed be 300r/min under conditions of ball milling 1h.Other are identical with embodiment six to one of 15.
Embodiment 17：Present embodiment from unlike embodiment six to one of 16：Step 4
In pressure be 20MPa under conditions of cold pressing idiosome is made.Other are identical with embodiment six to one of 16.
Embodiment 18：Present embodiment from unlike embodiment six to one of 17：Step 4
In be 660 DEG C in hot pressing temperature and pressure is hot pressed sintering 2.5h under conditions of 90MPa.Other and embodiment six to ten
One of seven is identical.
Embodiment 19：Present embodiment from unlike embodiment six to one of 18：Step 4
In be 660 DEG C in hot pressing temperature and pressure is hot pressed sintering 2.5h under conditions of 100MPa.Other with embodiment six to
One of 18 is identical.
Embodiment 20：Present embodiment from unlike embodiment six to one of 19：Step 4
In be 660 DEG C in hot pressing temperature and pressure is hot pressed sintering 2.5h under conditions of 110MPa.Other with embodiment six to
One of 19 is identical.
Beneficial effects of the present invention are verified using following examples：
Embodiment one：A kind of preparation method of neutron absorber material is to carry out according to the following steps：
First, 15% boron carbide, 1%Gd powder and 84% pure aluminium powder are weighed by volume fraction；The boron carbide is that particle diameter is 5 μm
Boron carbide particles；
2nd, 15% boron carbide, 1%Gd powder and 84% pure aluminium powder weighed step one is respectively in the drying that temperature is 40 DEG C
24h is dried in case, dried boron carbide, dried Gd powder and dried pure aluminium powder is obtained；
3rd, dried boron carbide, dried Gd powder and the mixing of dried pure aluminium powder obtained step 2, then
The ball milling 1h under conditions of rotating speed is 300r/min, obtains mixed powder；By mixed powder in temperature in 40 DEG C of drying box
24h is dried, dry powder is obtained；
4th, the powder for the drying for obtaining step 3 is fitted into mould, and embryo is made in cold pressing under conditions of pressure is 10MPa
Body, is then put into hot-pressed sintering furnace together with mould, is 660 DEG C in hot pressing temperature and pressure is heat under conditions of 80MPa
Pressure sintering 2.5h, after furnace cooling, the demoulding obtains neutron absorber material.
Embodiment two：A kind of B4The preparation method of C/Al composites is to carry out according to the following steps：
First, 15% boron carbide and 85% pure aluminium powder are weighed by volume fraction；The boron carbide is the boron carbide that particle diameter is 5 μm
Particle；
2nd, 15% boron carbide and 85% pure aluminium powder weighed step one dries 24h in temperature is 40 DEG C of drying box,
Obtain dried boron carbide and dried pure aluminium powder；
3rd, the dried boron carbide obtained step 2 and the mixing of dried pure aluminium powder, are then 300r/ in rotating speed
Ball milling 1h under conditions of min, obtains mixed powder；Mixed powder is dried into 24h in temperature is 40 DEG C of drying box, done
Dry powder；
4th, the powder for the drying for obtaining step 3 is fitted into mould, and embryo is made in cold pressing under conditions of pressure is 10MPa
Body, is then put into hot-pressed sintering furnace together with mould, is 660 DEG C in hot pressing temperature and pressure is to enter under conditions of 80MPa
Row hot pressed sintering, is then incubated 2.5h, after furnace cooling, the demoulding obtains B under conditions of pressure is 80MPa4C/Al composite woods
Material.
Embodiment three：The present embodiment and the difference of embodiment two are：In step one 30% is weighed by volume fraction
Boron carbide and 70% pure aluminium powder.Other are identical with embodiment two.
Example IV：A kind of preparation method of neutron absorber material is to carry out according to the following steps：
First, 15% boron carbide, 1%Gd powder and 84% pure aluminium powder are weighed by volume fraction；The boron carbide is that particle diameter is
17.5 μm of boron carbide particles；
2nd, 15% boron carbide, 1%Gd powder and 84% pure aluminium powder weighed step one is in temperature in 40 DEG C of drying box
24h is dried, dried boron carbide, dried Gd powder and dried pure aluminium powder is obtained；
3rd, dried boron carbide, dried Gd powder and the mixing of dried pure aluminium powder obtained step 2, then
The ball milling 1h under conditions of rotating speed is 300r/min, obtains mixed powder；By mixed powder in temperature in 40 DEG C of drying box
24h is dried, dry powder is obtained；
4th, the powder for the drying for obtaining step 3 is fitted into mould, and embryo is made in cold pressing under conditions of pressure is 10MPa
Body, is then put into hot-pressed sintering furnace together with mould, is 660 DEG C in hot pressing temperature and pressure is to enter under conditions of 80MPa
Row hot pressed sintering, is then incubated 2.5h, after furnace cooling, the demoulding obtains neutron absorber material under conditions of pressure is 80MPa.
Fig. 1 is the stress strain curve figure for the neutron absorber material that embodiment one is obtained；From the figure, it can be seen that the material has
Good plasticity, elongation percentage is up to 8%, it is easy to the machine-shaping of material.
The B that Fig. 2 is embodiment one is obtained under the conditions of Am-Be neutron sources neutron absorber material, embodiment two is obtained4C/
The B that Al composites and embodiment three are obtained4The shielding properties correlation curve of C/Al composites；Wherein 1 is that embodiment one is obtained
The neutron absorber material arrived, 2 be the B that embodiment two is obtained4C/Al composites, 3 be the B that embodiment three is obtained4C/Al composite woods
Material；From the figure, it can be seen that the Gd of 1% content of addition, the neutron absorber material that embodiment one is obtained is for Am-Be neutron sources
Neutron-absorbing effect is far better than the neutron absorber material that embodiment two is obtained, and its shielding properties can be obtained with embodiment three
To neutron absorber material compare favourably, this explanation, Gd addition is while neutron shield ability is ensured, in can effectively reducing
The content of boron carbide in sub- absorbing material, improves the plasticity of material, significant for its processed and applied.
Claims (3)
1. a kind of preparation method of neutron absorber material, it is characterised in that the preparation method of neutron absorber material is according to the following steps
Carry out：
First, 10%~20% boron carbide, 1%~2% neutron-absorbing material and 78%~89% alumina-bearing material are weighed by volume fraction；
The boron carbide is the boron carbide particles that particle diameter is 5 μm；Described alumina-bearing material is aluminum or aluminum alloy；
2nd, 10%~20% boron carbide, 1%~2% neutron-absorbing material and 78%~89% alumina-bearing material weighed step one
24h~36h is dried in temperature is 35 DEG C~50 DEG C of drying box respectively, dried boron carbide, dried neutron is obtained
Absorbent and dried alumina-bearing material；
3rd, dried boron carbide, dried neutron-absorbing material and the mixing of dried alumina-bearing material obtained step 2,
Then ball milling 0.5h~2h under conditions of rotating speed is 250r/min~350r/min, obtains mixed powder；Mixed powder is existed
Temperature obtains dry powder to dry 24h~36h in 35 DEG C~50 DEG C of drying box；
4th, the powder for the drying for obtaining step 3 is fitted into mould, the cold compaction under conditions of pressure is 10MPa~30MPa
Into idiosome, then it is put into together with mould in hot-pressed sintering furnace, be 660 DEG C~700 DEG C in hot pressing temperature is with pressure
Hot pressed sintering 2.5h under conditions of 100MPa, after furnace cooling, the demoulding obtains neutron absorber material；
Neutron-absorbing material described in step one is Gd；
When using the neutron absorber material that thickness is 1% for 2mm Gd volume fractions to carry out neutron absorption, counted using MCNP
Calculate, its absorptivity is more than 99%.
2. a kind of preparation method of neutron absorber material according to claim 1, it is characterised in that aluminium described in step one
Alloy is 1xxx line aluminium alloys, 2xxx line aluminium alloys, 3xxx line aluminium alloys, 4xxx line aluminium alloys, 5xxx line aluminium alloys or 6xxx
Line aluminium alloy.
3. the preparation method of a kind of neutron absorber material according to claim 1, it is characterised in that in pressure in step 4
Idiosome is made for cold pressing under conditions of 20MPa.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510701250.2A CN105200274B (en) | 2015-10-26 | 2015-10-26 | A kind of preparation method of neutron absorber material |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201510701250.2A CN105200274B (en) | 2015-10-26 | 2015-10-26 | A kind of preparation method of neutron absorber material |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN105200274A CN105200274A (en) | 2015-12-30 |
| CN105200274B true CN105200274B (en) | 2017-10-03 |
Family
ID=54948226
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201510701250.2A Active CN105200274B (en) | 2015-10-26 | 2015-10-26 | A kind of preparation method of neutron absorber material |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN105200274B (en) |
Families Citing this family (15)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105671373A (en) * | 2016-03-11 | 2016-06-15 | 江苏海龙核科技股份有限公司 | Preparing method for neutron absorption plate with high B4C content |
| CN106003373B (en) * | 2016-06-02 | 2018-01-26 | 东莞理工学院 | A kind of square tube type neutron absorbing layer mould and its forming method |
| CN106756164A (en) * | 2016-11-30 | 2017-05-31 | 中国科学院金属研究所 | A kind of thermal structure function integration B4The preparation method of C/Al neutron absorber materials |
| CN106756281B (en) * | 2017-01-20 | 2019-10-25 | 镇江纽科利核能新材料科技有限公司 | A kind of neutron absorber material of high rare-earth content and preparation method thereof |
| CN107164755B (en) * | 2017-05-18 | 2019-04-12 | 江苏广川线缆股份有限公司 | The spraying method of neutron absorption composite material on a kind of stainless steel substrate |
| CN107236330A (en) * | 2017-05-18 | 2017-10-10 | 江苏广川线缆股份有限公司 | A kind of Antiradiation dusts |
| CN108342620A (en) * | 2018-01-26 | 2018-07-31 | 安徽省鸣新材料科技有限公司 | A kind of foamed aluminium for shielding neutron and electronics |
| CN108484208B (en) * | 2018-03-07 | 2021-02-26 | 南京航空航天大学 | Mullite/corundum-based neutron shielding foamed ceramic for spent fuel storage and transportation and preparation method thereof |
| CN109504926B (en) * | 2018-10-09 | 2021-04-09 | 镇江华核装备有限公司 | Preparation process of novel boron carbide-aluminum alloy composite material plate with integrated structure and function |
| CN109559837A (en) * | 2018-10-09 | 2019-04-02 | 镇江华核装备有限公司 | A kind of used by nuclear reactor secondary shield neutron absorber plate |
| 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 |
| CN109797308A (en) * | 2019-01-30 | 2019-05-24 | 中广核工程有限公司 | A kind of new oxide dispersion-strengtherning neutron absorber material |
| CN109797309A (en) * | 2019-01-30 | 2019-05-24 | 中广核工程有限公司 | A kind of structure-function integration neutron absorber material High-Temperature Strengthening method |
| CN113862524A (en) * | 2021-10-14 | 2021-12-31 | 中硼科技(威海)有限公司 | Nuclear rare earth modified aluminum-based boron carbide material and preparation method thereof |
| CN114351010B (en) * | 2021-12-31 | 2023-01-10 | 清华大学深圳国际研究生院 | Aluminum-based boron carbide composite material and preparation method and application thereof |
Family Cites Families (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN1032833C (en) * | 1992-12-26 | 1996-09-18 | 天津纺织工学院 | Neutron and gamma-ray radiation shielding material |
| CA2563444C (en) * | 2004-04-22 | 2010-09-21 | Alcan International Limited | Improved neutron absorption effectiveness for boron content aluminum materials |
| CN102094132B (en) * | 2010-12-28 | 2012-07-11 | 中国工程物理研究院核物理与化学研究所 | Method for preparing B4C-Al composite material |
| CN102280156B (en) * | 2011-06-21 | 2013-09-18 | 大连宝原核设备有限公司 | Method for preparing aluminum-based boron carbide neutron absorption board |
| CN104313400B (en) * | 2014-10-20 | 2016-09-28 | 清华大学深圳研究生院 | A kind of Boral based composites and neutron absorber plate |
| CN104946911B (en) * | 2015-06-29 | 2017-03-08 | 哈尔滨工业大学 | A kind of spent fuel storage rack high-volume fractional B4The preparation method of C/Al composite |
-
2015
- 2015-10-26 CN CN201510701250.2A patent/CN105200274B/en active Active
Also Published As
| Publication number | Publication date |
|---|---|
| CN105200274A (en) | 2015-12-30 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN105200274B (en) | A kind of preparation method of neutron absorber material | |
| CN103045916B (en) | Composite shielding material and preparation method thereof | |
| CN104946911B (en) | A kind of spent fuel storage rack high-volume fractional B4The preparation method of C/Al composite | |
| TW497104B (en) | Aluminum composite material, aluminum composite powder and its manufacturing method, spent fuel storage member and its manufacturing method | |
| CN102703742B (en) | Metal-based composite material with substrate of nano laminated structure and preparation method thereof | |
| CN106756164A (en) | A kind of thermal structure function integration B4The preparation method of C/Al neutron absorber materials | |
| CN103276254B (en) | A kind of composite shielding material and preparation method thereof | |
| CN111205067B (en) | Glass-ceramic material for cooperative protection of neutrons and gamma rays and preparation method thereof | |
| CN108130438B (en) | Preparation method of high-temperature structure function integrated boron carbide reinforced aluminum-based neutron absorption material | |
| CN106756281B (en) | A kind of neutron absorber material of high rare-earth content and preparation method thereof | |
| CN109852850A (en) | A kind of preparation method of structure-function integration neutron absorber material | |
| CN110415845B (en) | High-uranium-density composite fuel pellet and preparation method thereof | |
| CN108335760A (en) | A kind of preparation method of high uranium useful load dispersion fuel pellet | |
| CN104308161B (en) | Preparation method of boron carbide/aluminum composite board | |
| CN106978563B (en) | A kind of Al-B4C-B neutron absorber materials and preparation method thereof | |
| CN109797309A (en) | A kind of structure-function integration neutron absorber material High-Temperature Strengthening method | |
| CN102110484B (en) | Method for preparing B4C-Al neutron-absorbing plate for spent fuel storage and transportation | |
| CN109797308A (en) | A kind of new oxide dispersion-strengtherning neutron absorber material | |
| CN111910113A (en) | Boron-containing particle reinforced tungsten-aluminum alloy composite shielding material and preparation method thereof | |
| CN109825743A (en) | A kind of application method of structure-function integration neutron absorber material | |
| TW552590B (en) | Method of manufacturing a radioactive-substance storage member, billet for use in extrusion of the same, and square pipe | |
| WO2019085593A1 (en) | Fuel pellet manufacturing method and fuel pellet | |
| CN111205107A (en) | Radiation shielding composite material and preparation method thereof | |
| CN100335664C (en) | Shielded Pb-base composite materials with high-energy ray and production thereof | |
| WO2020150976A1 (en) | Coated fuel particle, inert matrix dispersed fuel pellet and integrated fuel rod, and fabrication methods therefor |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| C06 | Publication | ||
| PB01 | Publication | ||
| C10 | Entry into substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |