CN105200274A - Neutron absorbing material and preparation method thereof - Google Patents
Neutron absorbing material and preparation method thereof Download PDFInfo
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- CN105200274A CN105200274A CN201510701250.2A CN201510701250A CN105200274A CN 105200274 A CN105200274 A CN 105200274A CN 201510701250 A CN201510701250 A CN 201510701250A CN 105200274 A CN105200274 A CN 105200274A
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Abstract
A neutron absorbing material and its preparation method relate to a neutron absorbing material and its preparation method. The invention aims to solve the problem that existing spent fuel shielding materials cannot ensure neutron shielding property of a composite material, and plasticity of a composite material can be enhanced. The neutron absorbing material is prepared from, by volume, 10-20% of boron carbide, 1-2% of a neutron absorber and 78-89% of aluminium or aluminium alloy. The preparation method comprises the following steps: 1, weighing; 2, drying; 3, ball-milling and mixing; and 4, cold pressing for blank-making and hot pressed sintering. The neutron absorbing material prepared in the invention has high shielding property, has good plasticity, is easy for machine-shaping, can meet requirements of densification and long-term tendency for spent fuel storage, and is an ideal spent fuel storage grid material. The neutron absorbing material of the invention is used in the field of neutron radiation shielding in nuclear industry.
Description
Technical field
The present invention relates to a kind of neutron absorber material and preparation method thereof.
Background technology
Nuclear fuel can become spent fuel after using, and has very high neutron radiation effect, can produce serious radiation pollution if deal with improperly to surrounding environment.Along with the fast development of nuclear industry, increasing Nuclear power plants comes into operation all in succession, also the generation of a large amount of spent fuels will be caused, due to the limited of storage space and the prolongation of reactor working life, nuclear industry is faced with the challenge of spent fuel highly denseization, long life storage, therefore propose higher service requirements to spent fuel storage rack, namely neutron absorption capability is strong, can meet that spent fuel is highly dense, the requirement of long storage periods.Therefore the exploitation material with outstanding neutron absorption capability is solve the most effective means of following irradiated fuel store Critical Control problem as spent fuel storage rack material.
Conventional neutron shielding material has aluminum-boron alloy, boron steel, Boron-containing-PE and B
4c/Al matrix material etc.Aluminum-boron alloy and boron steel are all limited due to its boron-containing quantity, cannot meet the requirement of spent fuel high density storage; Boron-containing-PE due to matrix be polymkeric substance, therefore mechanical property is general, easily aging embrittlement occurs simultaneously, causes its work-ing life short.B
4c/Al matrix material is due to its low density, and good mechanical property, can pass through process adjustments B simultaneously
4c content improves the ability absorbing thermal neutron, becomes outstanding thermal neutron shielding material.Two kinds of the most frequently used in the world spent fuel storage rack materials, namely BORAL and METAMIC is B
4c/Al matrix material.BORAL is by the boron carbide powder that mixes and aluminium powder, put into the aluminium alloy box that welded seal is good, obtaining levels by the technique of hot rolling is aluminium sheet, middle layer is the sheet material of mixed uniformly boron carbide powder and aluminium powder, and the feature of BORAL is very high containing norbide amount, can reach 65%, but shortcoming is because its mixed powder is not through oversintering, density is low, and plasticity is poor, in use easily the phenomenons such as foaming occurs simultaneously.METAMIC adopts powder metallurgical technique, by aluminium powder and boron carbide powder mixing, adopts the techniques such as isostatic cool pressing, vacuum sintering and extruding to be prepared into B
4c/Al matrix material, it is containing norbide amount high less than BORAL (45wt%), and complicated process of preparation, high to equipment requirements simultaneously.
Domestic in recent years to B
4c/Al matrix material starts large quantity research.The patent No. is CN102392148A, denomination of invention be adopt mixed powder in " a kind of preparation method of aluminum-based boron carbide neutron absorption composite material ", B that cold pressing base and sintering process have prepared different content norbide amount
4c/Al matrix material.
The patent No. is CN102280156A, denomination of invention is the mode adopting ball milling in " a kind of preparation method of aluminum-based boron carbide neutron absorption board ", by aluminium powder, boron carbide powder, titanium valve, silica flour and the boric acid crystal mixing after oxidation, the mode of powder metallurgy and hot extrusion is adopted to make B
4c/Al composite board.But matrix material unit elongation is low, only has 1.8%, it is shaping to be not easy to secondary processing.
The patent No. is CN102094132A, and denomination of invention is " B
4c-Al composite material and preparation method thereof " in, adopt mixed powder, base of colding pressing, the technique of vacuum sintering and repeatedly hot rolling prepared containing B
4the B of C amount 5% ~ 35%
4c-Al matrix material, inventive result shows, when norbide content is less, when being only 15%, matrix material has outstanding plasticity, and unit elongation is up to 10%, but along with the increase of norbide content, plasticity declines obviously, when norbide content reaches 30%, the unit elongation of matrix material is less than 2%, that is, along with the increase of norbide content, the neutron shield performance of matrix material raises, but plasticity declines, and is unfavorable for the hot-work of material.
The patent No. is CN102110484B, and denomination of invention is " a kind of spent fuel storing B
4the preparation method of C-Al neutron absorber plate " in, same adopt mixed powder, cold pressing base and sintering process have prepared B containing 10wt% ~ 65wt%
4c-Al matrix material, and loaded welded seal in aluminum alloy frame and carry out hot rolling again, finally obtained B
4c-Al neutron absorber plate.There are the problems referred to above equally, namely high carbonization Boron contents makes the plasticity of matrix material sharply decline, after hot rolling containing 35% matrix material unit elongation only have 4.1%, simultaneously density only has 96.8%.
Can find from above research, B
4c/Al matrix material, due to its outstanding neutron-absorbing performance, has boundless application potential for spent fuel shielding material, also very extensive to this research both at home and abroad, but the feature of face the future irradiated fuel store highly denseization, long life, improve B
4c content, namely improves the neutron shield performance of matrix material, for B
4c/Al matrix material is the only way which must be passed.But too much norbide will certainly cause the plasticity of material to decline, and is unfavorable for the machine-shaping of matrix material.When norbide content is more than 30%, the situation that this plasticity declines becomes obvious especially, and material density also can decline simultaneously.And too low norbide content cannot effectively ensure neutron shield performance.Therefore, how while guarantee matrix material neutron shield performance, the plasticity improving matrix material is B
4the problem that C/Al matrix material must solve as spent fuel storage rack Materials.
Summary of the invention
The present invention will solve existing spent fuel shielding material ensureing matrix material neutron shield performance while, cannot can improve again the problem of the plasticity of matrix material, and provide a kind of neutron absorber material and preparation method thereof.
A kind of neutron absorber material of the present invention by volume mark is made up of 10% ~ 20% norbide, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material; Described norbide to be particle diameter the be boron carbide particles of 17.5 μm or particle diameter are the boron carbide particles of 5 μm; Described alumina-bearing material is aluminum or aluminum alloy.
The preparation method of a kind of neutron absorber material of the present invention carries out according to the following steps:
One, by volume mark takes 10% ~ 20% norbide, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material; Described norbide to be particle diameter the be boron carbide particles of 17.5 μm or particle diameter are the boron carbide particles of 5 μm;
Two, 10% ~ 20% norbide step one taken, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material are dry 24h ~ 36h in the loft drier of 35 DEG C ~ 50 DEG C respectively in temperature, obtain dried norbide, dried neutron-absorbing material and dried alumina-bearing material;
Three, dried norbide step 2 obtained, dried neutron-absorbing material and dried alumina-bearing material mix, and are then ball milling 0.5h ~ 2h under the condition of 250r/min ~ 350r/min at rotating speed, obtain mixed powder; Be dry 24h ~ 36h in the loft drier of 35 DEG C ~ 50 DEG C in temperature by mixed powder, obtain dry powder;
The powder of the drying four, step 3 obtained loads in mould, be cold pressing under the condition of 10MPa ~ 30MPa to make idiosome at pressure, then hot-pressed sintering furnace is put into together with mould, hot pressed sintering 2h ~ 3h under hot pressing temperature is 600 DEG C ~ 700 DEG C and pressure is the condition of 80MPa ~ 120MPa, after furnace cooling, the demoulding obtains neutron absorber material.
The invention has the beneficial effects as follows:
Neutron absorber material density of the present invention is high, because norbide content is about 10% ~ 20%, not only serves good reinforced effects, can play the plasticity of aluminium alloy simultaneously, and the plasticity of matrix material is better, is easy to machine-shaping; Simultaneously owing to the addition of the element particle in high neutron absorption cross section in neutron absorber material, improve the receptivity of matrix material to neutron; The neutron absorber material prepared, have excellent mechanical property, unit elongation can reach 8%, is far more than the B of equal norbide content both at home and abroad
4c/Al matrix material, there is outstanding neutron-absorbing performance simultaneously, adopt MCNP calculate, Gd volume fraction be 1% neutron absorber material only 2mm thick just can shield more than 99% thermal neutron, China can be met at present and even future, the demand of irradiated fuel store highly denseization, long life.
Accompanying drawing explanation
Fig. 1 is the stress strain curve figure of the neutron absorber material that embodiment one obtains;
The B that Fig. 2 is embodiment one obtains under Am-Be neutron source condition neutron absorber material, embodiment two obtains
4the B that C/Al matrix material and embodiment three obtain
4the shielding properties correlation curve of C/Al matrix material; Wherein 1 is the neutron absorber material that embodiment one obtains, and 2 is the B that embodiment two obtains
4c/Al matrix material, 3 is the B that embodiment three obtains
4c/Al matrix material.
Embodiment
Embodiment one: a kind of neutron absorber material of present embodiment by volume mark is made up of 10% ~ 20% norbide, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material; Described norbide to be particle diameter the be boron carbide particles of 17.5 μm or particle diameter are the boron carbide particles of 5 μm; Described alumina-bearing material is aluminum or aluminum alloy.
The neutron absorber material density of present embodiment is high, because norbide content is about 10% ~ 20%, not only serves good reinforced effects, can play the plasticity of aluminium alloy simultaneously, and the plasticity of matrix material is better, is easy to machine-shaping; Simultaneously owing to the addition of the element particle in high neutron absorption cross section in neutron absorber material, improve the receptivity of matrix material to neutron; The neutron absorber material prepared, have excellent mechanical property, unit elongation can reach 8%, is far more than the B of equal norbide content both at home and abroad
4c/Al matrix material, there is outstanding neutron-absorbing performance simultaneously, adopt MCNP calculate, Gd volume fraction be 1% neutron absorber material only 2mm thick just can shield more than 99% thermal neutron, China can be met at present and even future, the demand of irradiated fuel store highly denseization, long life.
Embodiment two: present embodiment and embodiment one unlike: neutron absorber material by volume mark is made up of 14% ~ 16% norbide, 1% neutron-absorbing material and 83% ~ 85% alumina-bearing material.Other are identical with embodiment one.
Embodiment three: present embodiment and embodiment one or two unlike: neutron absorber material by volume mark is made up of 15% norbide, 1% neutron-absorbing material and 84% alumina-bearing material.Other are identical with embodiment one or two.
Embodiment four: one of present embodiment and embodiment one to three unlike: described neutron-absorbing material is Gd, Cd, Sm, Eu, Gd compound, Cd compound, Sm compound or Eu compound.Other are identical with one of embodiment one to three.
Embodiment five: one of present embodiment and embodiment one to four unlike: described aluminium alloy is 1xxx line aluminium alloy, 2xxx line aluminium alloy, 3xxx line aluminium alloy, 4xxx line aluminium alloy, 5xxx line aluminium alloy or 6xxx line aluminium alloy.Other are identical with one of embodiment one to four.
Embodiment six: the preparation method of a kind of neutron absorber material of present embodiment carries out according to the following steps:
One, by volume mark takes 10% ~ 20% norbide, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material; Described norbide to be particle diameter the be boron carbide particles of 17.5 μm or particle diameter are the boron carbide particles of 5 μm; Described alumina-bearing material is aluminum or aluminum alloy;
Two, 10% ~ 20% norbide step one taken, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material are dry 24h ~ 36h in the loft drier of 35 DEG C ~ 50 DEG C respectively in temperature, obtain dried norbide, dried neutron-absorbing material and dried alumina-bearing material;
Three, dried norbide step 2 obtained, dried neutron-absorbing material and dried alumina-bearing material mix, and are then ball milling 0.5h ~ 2h under the condition of 250r/min ~ 350r/min at rotating speed, obtain mixed powder; Be dry 24h ~ 36h in the loft drier of 35 DEG C ~ 50 DEG C in temperature by mixed powder, obtain dry powder;
The powder of the drying four, step 3 obtained loads in mould, be cold pressing under the condition of 10MPa ~ 30MPa to make idiosome at pressure, then hot-pressed sintering furnace is put into together with mould, hot pressed sintering 2h ~ 3h under hot pressing temperature is 600 DEG C ~ 700 DEG C and pressure is the condition of 80MPa ~ 120MPa, after furnace cooling, the demoulding obtains neutron absorber material.
The neutron absorber material density of present embodiment is high, because norbide content is about 10% ~ 20%, not only serves good reinforced effects, can play the plasticity of aluminium alloy simultaneously, and the plasticity of matrix material is better, is easy to machine-shaping; Simultaneously owing to the addition of the element particle in high neutron absorption cross section in neutron absorber material, improve the receptivity of matrix material to neutron; The neutron absorber material prepared, have excellent mechanical property, unit elongation can reach 8%, is far more than the B of equal norbide content both at home and abroad
4c/Al matrix material, there is outstanding neutron-absorbing performance simultaneously, adopt MCNP calculate, Gd volume fraction be 1% neutron absorber material only 2mm thick just can shield more than 99% thermal neutron, China can be met at present and even future, the demand of irradiated fuel store highly denseization, long life.
Embodiment seven: present embodiment and embodiment six unlike: in step one, by volume mark takes 10% ~ 14% norbide, 1% neutron-absorbing material and 85% ~ 89% alumina-bearing material.Other are identical with embodiment six.
Embodiment eight: present embodiment and embodiment six or seven unlike: in step one, by volume mark takes 15% ~ 19% norbide, 1% neutron-absorbing material and 80% ~ 84% alumina-bearing material.Other are identical with embodiment six or seven.
Embodiment nine: one of present embodiment and embodiment six to eight unlike: in step one, by volume mark takes 20% norbide, 1% neutron-absorbing material and 79% alumina-bearing material.Other are identical with one of embodiment six to eight.
Embodiment ten: one of present embodiment and embodiment six to nine unlike: in step one, by volume mark takes 10% ~ 14% norbide, 2% neutron-absorbing material and 84% ~ 88% alumina-bearing material.Other are identical with one of embodiment six to nine.
Embodiment 11: one of present embodiment and embodiment six to ten unlike: in step one, by volume mark takes 15% ~ 19% norbide, 2% neutron-absorbing material and 79% ~ 83% alumina-bearing material.Other are identical with one of embodiment six to ten.
Embodiment 12: one of present embodiment and embodiment six to ten one unlike: in step one, by volume mark takes 20% norbide, 2% neutron-absorbing material and 78% alumina-bearing material.Other are identical with one of embodiment six to ten one.
Embodiment 13: one of present embodiment and embodiment six to ten two unlike: neutron-absorbing material described in step one is Gd, Cd, Sm, Eu, Gd compound, Cd compound, Sm compound or Eu compound.Other are identical with one of embodiment six to ten two.
Embodiment 14: one of present embodiment and embodiment six to ten three unlike: aluminium alloy described in step one is 1xxx line aluminium alloy, 2xxx line aluminium alloy, 3xxx line aluminium alloy, 4xxx line aluminium alloy, 5xxx line aluminium alloy or 6xxx line aluminium alloy.Other are identical with one of embodiment six to ten three.
Embodiment 15: one of present embodiment and embodiment six to ten four unlike: be dry 24h in the loft drier of 40 DEG C in temperature in step 2.Other are identical with one of embodiment six to ten four.
Embodiment 16: one of present embodiment and embodiment six to ten five unlike: be ball milling 1h under the condition of 300r/min at rotating speed in step 3.Other are identical with one of embodiment six to ten five.
Embodiment 17: one of present embodiment and embodiment six to ten six unlike: be cold pressing under the condition of 20MPa to make idiosome at pressure in step 4.Other are identical with one of embodiment six to ten six.
Embodiment 18: one of present embodiment and embodiment six to ten seven are unlike hot pressed sintering 2.5h under be 660 DEG C and pressure being the condition of 90MPa in hot pressing temperature in step 4.Other are identical with one of embodiment six to ten seven.
Embodiment 19: one of present embodiment and embodiment six to ten eight are unlike hot pressed sintering 2.5h under be 660 DEG C and pressure being the condition of 100MPa in hot pressing temperature in step 4.Other are identical with one of embodiment six to ten eight.
Embodiment 20: one of present embodiment and embodiment six to ten nine are unlike hot pressed sintering 2.5h under be 660 DEG C and pressure being the condition of 110MPa in hot pressing temperature in step 4.Other are identical with one of embodiment six to ten nine.
Following examples are adopted to verify beneficial effect of the present invention:
Embodiment one: a kind of preparation method of neutron absorber material carries out according to the following steps:
One, by volume mark takes 15% norbide, 1%Gd powder and 84% pure aluminium powder; Described norbide to be particle diameter the be boron carbide particles of 5 μm;
Two, 15% norbide step one taken, 1%Gd powder and 84% pure aluminium powder are dry 24h in the loft drier of 40 DEG C respectively in temperature, obtain dried norbide, dried Gd powder and dried pure aluminium powder;
Three, dried norbide step 2 obtained, dried Gd powder and dried pure aluminium powder mix, and are then ball milling 1h under the condition of 300r/min at rotating speed, obtain mixed powder; Be dry 24h in the loft drier of 40 DEG C in temperature by mixed powder, obtain dry powder;
The powder of the drying four, step 3 obtained loads in mould, be cold pressing under the condition of 10MPa to make idiosome at pressure, then hot-pressed sintering furnace is put into together with mould, hot pressed sintering 2.5h under hot pressing temperature is 660 DEG C and pressure is the condition of 80MPa, after furnace cooling, the demoulding obtains neutron absorber material.
Embodiment two: a kind of B
4the preparation method of C/Al matrix material carries out according to the following steps:
One, by volume mark takes 15% norbide and 85% pure aluminium powder; Described norbide to be particle diameter the be boron carbide particles of 5 μm;
Two, 15% norbide step one taken and 85% pure aluminium powder are dry 24h in the loft drier of 40 DEG C in temperature, obtain dried norbide and dried pure aluminium powder;
Three, dried norbide step 2 obtained and the mixing of dried pure aluminium powder, be then ball milling 1h under the condition of 300r/min at rotating speed, obtain mixed powder; Be dry 24h in the loft drier of 40 DEG C in temperature by mixed powder, obtain dry powder;
The powder of the drying four, step 3 obtained loads in mould, be cold pressing under the condition of 10MPa to make idiosome at pressure, then hot-pressed sintering furnace is put into together with mould, hot pressed sintering is carried out under hot pressing temperature is 660 DEG C and pressure is the condition of 80MPa, then be incubated 2.5h under the condition of 80MPa at pressure, after furnace cooling, the demoulding obtains B
4c/Al matrix material.
Embodiment three: the difference of the present embodiment and embodiment two is: in step one, by volume mark takes 30% norbide and 70% pure aluminium powder.Other are identical with embodiment two.
Embodiment four: a kind of preparation method of neutron absorber material carries out according to the following steps:
One, by volume mark takes 15% norbide, 1%Gd powder and 84% pure aluminium powder; Described norbide to be particle diameter the be boron carbide particles of 17.5 μm;
Two, 15% norbide step one taken, 1%Gd powder and 84% pure aluminium powder are dry 24h in the loft drier of 40 DEG C in temperature, obtain dried norbide, dried Gd powder and dried pure aluminium powder;
Three, dried norbide step 2 obtained, dried Gd powder and dried pure aluminium powder mix, and are then ball milling 1h under the condition of 300r/min at rotating speed, obtain mixed powder; Be dry 24h in the loft drier of 40 DEG C in temperature by mixed powder, obtain dry powder;
The powder of the drying four, step 3 obtained loads in mould, be cold pressing under the condition of 10MPa to make idiosome at pressure, then hot-pressed sintering furnace is put into together with mould, hot pressed sintering is carried out under hot pressing temperature is 660 DEG C and pressure is the condition of 80MPa, then be incubated 2.5h under the condition of 80MPa at pressure, after furnace cooling, the demoulding obtains neutron absorber material.
Fig. 1 is the stress strain curve figure of the neutron absorber material that embodiment one obtains; As we can see from the figure, this material has good plasticity, and unit elongation can reach 8%, is easy to the machine-shaping of material.
The B that Fig. 2 is embodiment one obtains under Am-Be neutron source condition neutron absorber material, embodiment two obtains
4the B that C/Al matrix material and embodiment three obtain
4the shielding properties correlation curve of C/Al matrix material; Wherein 1 is the neutron absorber material that embodiment one obtains, and 2 is the B that embodiment two obtains
4c/Al matrix material, 3 is the B that embodiment three obtains
4c/Al matrix material; As we can see from the figure, add the Gd of 1% content, the neutron absorber material that embodiment one obtains is better than for the neutron-absorbing effect of Am-Be neutron source the neutron absorber material that embodiment two obtains far away, the neutron absorber material that its shielding properties can obtain with embodiment three compares favourably, this illustrates, while being added on of Gd ensures neutron shield ability, effectively can reduce the content of norbide in neutron absorber material, improve the plasticity of material, significant for its processed and applied.
Claims (10)
1. a neutron absorber material, it is characterized in that neutron absorber material by volume mark be made up of 10% ~ 20% norbide, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material; Described norbide to be particle diameter the be boron carbide particles of 17.5 μm or particle diameter are the boron carbide particles of 5 μm; Described alumina-bearing material is aluminum or aluminum alloy.
2. a kind of neutron absorber material according to claim 1, it is characterized in that neutron absorber material by volume mark be made up of 14% ~ 16% norbide, 1% neutron-absorbing material and 83% ~ 85% alumina-bearing material.
3. a kind of neutron absorber material according to claim 1, it is characterized in that neutron absorber material by volume mark be made up of 15% norbide, 1% neutron-absorbing material and 84% alumina-bearing material.
4. a kind of neutron absorber material according to claim 1, is characterized in that described neutron-absorbing material is Gd, Cd, Sm, Eu, Gd compound, Cd compound, Sm compound or Eu compound.
5. a kind of neutron absorber material according to claim 1, is characterized in that described aluminium alloy is 1xxx line aluminium alloy, 2xxx line aluminium alloy, 3xxx line aluminium alloy, 4xxx line aluminium alloy, 5xxx line aluminium alloy or 6xxx line aluminium alloy.
6. the preparation method of a kind of neutron absorber material as claimed in claim 1, is characterized in that the preparation method of neutron absorber material carries out according to the following steps:
One, by volume mark takes 10% ~ 20% norbide, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material; Described norbide to be particle diameter the be boron carbide particles of 17.5 μm or particle diameter are the boron carbide particles of 5 μm; Described alumina-bearing material is aluminum or aluminum alloy;
Two, 10% ~ 20% norbide step one taken, 1% ~ 2% neutron-absorbing material and 78% ~ 89% alumina-bearing material are dry 24h ~ 36h in the loft drier of 35 DEG C ~ 50 DEG C respectively in temperature, obtain dried norbide, dried neutron-absorbing material and dried alumina-bearing material;
Three, dried norbide step 2 obtained, dried neutron-absorbing material and dried alumina-bearing material mix, and are then ball milling 0.5h ~ 2h under the condition of 250r/min ~ 350r/min at rotating speed, obtain mixed powder; Be dry 24h ~ 36h in the loft drier of 35 DEG C ~ 50 DEG C in temperature by mixed powder, obtain dry powder;
The powder of the drying four, step 3 obtained loads in mould, be cold pressing under the condition of 10MPa ~ 30MPa to make idiosome at pressure, then hot-pressed sintering furnace is put into together with mould, hot pressed sintering 2h ~ 3h under hot pressing temperature is 600 DEG C ~ 700 DEG C and pressure is the condition of 80MPa ~ 120MPa, after furnace cooling, the demoulding obtains neutron absorber material.
7. the preparation method of a kind of neutron absorber material according to claim 6, is characterized in that neutron-absorbing material described in step one is Gd, Cd, Sm, Eu, Gd compound, Cd compound, Sm compound or Eu compound.
8. the preparation method of a kind of neutron absorber material according to claim 6, is characterized in that aluminium alloy described in step one is 1xxx line aluminium alloy, 2xxx line aluminium alloy, 3xxx line aluminium alloy, 4xxx line aluminium alloy, 5xxx line aluminium alloy or 6xxx line aluminium alloy.
9. the preparation method of a kind of neutron absorber material according to claim 6, it is characterized in that colds pressing in step 4 under pressure is the condition of 20MPa makes idiosome.
10. the preparation method of a kind of neutron absorber material according to claim 6, it is characterized in that be 660 DEG C and pressure be the condition of 100MPa in hot pressing temperature in step 4 under hot pressed sintering 2.5h.
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