CN104611653B - Al B are used in a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials - Google Patents
Al B are used in a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials Download PDFInfo
- Publication number
- CN104611653B CN104611653B CN201510062108.8A CN201510062108A CN104611653B CN 104611653 B CN104611653 B CN 104611653B CN 201510062108 A CN201510062108 A CN 201510062108A CN 104611653 B CN104611653 B CN 104611653B
- Authority
- CN
- China
- Prior art keywords
- neutron absorber
- treatment
- temperature
- absorber materials
- heat treatment
- 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.)
- Expired - Fee Related
Links
- 239000000463 material Substances 0.000 title claims abstract description 68
- 238000000034 method Methods 0.000 title claims abstract description 53
- 239000006096 absorbing agent Substances 0.000 title claims abstract description 32
- 238000010438 heat treatment Methods 0.000 title claims abstract description 26
- 239000000446 fuel Substances 0.000 title claims abstract description 18
- 230000032683 aging Effects 0.000 claims abstract description 44
- 238000010791 quenching Methods 0.000 claims abstract description 16
- 230000000171 quenching effect Effects 0.000 claims abstract description 16
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 29
- 229910000838 Al alloy Inorganic materials 0.000 claims description 19
- 239000007787 solid Substances 0.000 claims description 15
- 239000011159 matrix material Substances 0.000 claims description 11
- 230000002708 enhancing effect Effects 0.000 claims description 2
- 239000007788 liquid Substances 0.000 claims description 2
- 239000002245 particle Substances 0.000 abstract description 5
- 239000000919 ceramic Substances 0.000 abstract description 4
- 230000007774 longterm Effects 0.000 abstract description 3
- 230000000750 progressive effect Effects 0.000 abstract description 3
- 238000002474 experimental method Methods 0.000 abstract description 2
- 239000002131 composite material Substances 0.000 description 38
- 229910052580 B4C Inorganic materials 0.000 description 26
- 239000000243 solution Substances 0.000 description 26
- 229910052796 boron Inorganic materials 0.000 description 15
- 230000000052 comparative effect Effects 0.000 description 14
- 229910045601 alloy Inorganic materials 0.000 description 11
- 239000000956 alloy Substances 0.000 description 11
- 238000000137 annealing Methods 0.000 description 11
- 238000003483 aging Methods 0.000 description 9
- 239000002915 spent fuel radioactive waste Substances 0.000 description 9
- 230000032258 transport Effects 0.000 description 8
- 230000035882 stress Effects 0.000 description 7
- 238000005275 alloying Methods 0.000 description 6
- 229910052802 copper Inorganic materials 0.000 description 6
- 239000012535 impurity Substances 0.000 description 6
- 229910052742 iron Inorganic materials 0.000 description 6
- 229910052748 manganese Inorganic materials 0.000 description 6
- 239000000203 mixture Substances 0.000 description 6
- 238000005096 rolling process Methods 0.000 description 6
- 238000003860 storage Methods 0.000 description 6
- 229910052725 zinc Inorganic materials 0.000 description 6
- 238000012545 processing Methods 0.000 description 5
- 229910001250 2024 aluminium alloy Inorganic materials 0.000 description 4
- 229910001094 6061 aluminium alloy Inorganic materials 0.000 description 4
- 229910052804 chromium Inorganic materials 0.000 description 4
- 229910019752 Mg2Si Inorganic materials 0.000 description 3
- 239000011358 absorbing material Substances 0.000 description 3
- XAGFODPZIPBFFR-UHFFFAOYSA-N aluminium Chemical compound [Al] XAGFODPZIPBFFR-UHFFFAOYSA-N 0.000 description 3
- 229910052782 aluminium Inorganic materials 0.000 description 3
- 230000000694 effects Effects 0.000 description 3
- 238000005098 hot rolling Methods 0.000 description 3
- 229910001008 7075 aluminium alloy Inorganic materials 0.000 description 2
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 2
- 238000004519 manufacturing process Methods 0.000 description 2
- 238000002360 preparation method Methods 0.000 description 2
- 238000011160 research Methods 0.000 description 2
- 239000006104 solid solution Substances 0.000 description 2
- 238000012360 testing method Methods 0.000 description 2
- 239000003082 abrasive agent Substances 0.000 description 1
- 238000013019 agitation Methods 0.000 description 1
- AZDRQVAHHNSJOQ-UHFFFAOYSA-N alumane Chemical compound [AlH3] AZDRQVAHHNSJOQ-UHFFFAOYSA-N 0.000 description 1
- 239000004411 aluminium Substances 0.000 description 1
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 1
- 238000003763 carbonization Methods 0.000 description 1
- 238000005266 casting Methods 0.000 description 1
- 150000001875 compounds Chemical class 0.000 description 1
- 238000005520 cutting process Methods 0.000 description 1
- 238000000151 deposition Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 230000018109 developmental process Effects 0.000 description 1
- 238000009792 diffusion process Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000001192 hot extrusion Methods 0.000 description 1
- 230000010354 integration Effects 0.000 description 1
- 238000005259 measurement Methods 0.000 description 1
- 229910052573 porcelain Inorganic materials 0.000 description 1
- 239000000843 powder Substances 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 239000000941 radioactive substance Substances 0.000 description 1
- 239000002994 raw material Substances 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 230000035939 shock Effects 0.000 description 1
- 230000002269 spontaneous effect Effects 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 239000000758 substrate Substances 0.000 description 1
- 239000010891 toxic waste Substances 0.000 description 1
Classifications
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/04—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of aluminium or alloys based thereon
Landscapes
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- Thermal Sciences (AREA)
- Crystallography & Structural Chemistry (AREA)
- Engineering & Computer Science (AREA)
- Materials Engineering (AREA)
- Mechanical Engineering (AREA)
- Metallurgy (AREA)
- Organic Chemistry (AREA)
- Manufacture Of Alloys Or Alloy Compounds (AREA)
Abstract
Al B are used the invention discloses a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials, it is therefore intended that effectively improve Al B4Stability of the C neutron absorber materials in the application process of high radioactivity place, it is ensured that its in use steady in a long-term.The method is including solution treatment, Quenching Treatment, Ageing Treatment etc..The present invention can be to Al B4C neutron absorber materials are heat-treated, and are effectively improved B4The distributing homogeneity of C ceramic particles, makes it obtain combination property higher, it is ensured that the stability and security of product longtime running.Experiment proves that, it is processed by the invention after material there is good microstructure, can effectively ensure that Al B4Stability and security of the C neutron absorber materials in the application process of high radioactivity place, with important progressive meaning.
Description
Technical field
The present invention relates to material heat treatment field, especially Al-B4The heat treatment method of C neutron absorber materials, it is one
Plant the heat treatment side for aluminum-based boron carbide composite shielding materials in nuclear radiation place such as nuclear reactor, irradiated fuel store and transports
Method.
Background technology
Planned according to national nuclear power developing, to the year two thousand twenty, China will produce about 1000 tons of spentnuclear fuels every year, and how safety is store
Depositing these has the high radioactivity, highly toxic waste will be as Tough questions.Neutron absorber material can pacify to spentnuclear fuel
Store entirely and transport, its neutron that can not only absorb spentnuclear fuel spontaneous decay generation, moreover it is possible to maintain spentnuclear fuel subcritical
State, prevents the diffusion of radioactive substance external environment.
The storage of spentnuclear fuel be divided into wet method storage and Dry storage, the former be by high radioactivity irradiated fuel store in having
In the pond of sub- absorbing material screen work, the latter be then by irradiated fuel store in the container tank prepared by neutron absorber material.This
Outward, during spentnuclear fuel being transported into reprocessing plant from coastal nuclear plant safety, in addition it is also necessary to which the transport that can shield neutron is held
Device.However, critical material of the country to irradiated fuel store --- the research of neutron absorber material relatively lags behind, slow.
Domestic existing Boron-containing-PE, boronated stainless steel isotonic absorbing material cannot meet generation Ⅲ nuclear power system
60 years service life, and storage density is relatively low.And Al-B4C composite has the plasticity and toughness of metallic aluminium, and carbonization concurrently
The advantages of high intensity, high rigidity, good neutron-absorbing effect of boron ceramics, be a kind of excellent structure-function integration material.
Using Al-B4The screen work of the Spent fuel pit that C neutron absorber materials make, can not only improve the storage density in pond, also
Neutron reaction can be effectively controlled, to maintain the subcritical state of spentnuclear fuel, it is ensured that the nuclear safety in storage process.And how to have
Effect improves Al-B4C neutron absorber materials are in the stability in the application process of high radioactivity place, it is ensured that it is in use
It is steady in a long-term, as the urgent concern of people.
The content of the invention
Goal of the invention of the invention is to effectively improve Al-B4C neutron absorber materials were applied in high radioactivity place
A kind of stability in journey, it is ensured that its in use steady in a long-term, there is provided irradiated fuel store and transport Al-B4In C
The heat treatment method of sub- absorbing material.The present invention can be to Al-B4C neutron absorber materials are heat-treated, and are effectively improved B4C makes pottery
The distributing homogeneity of porcelain particle, makes it obtain combination property higher, it is ensured that the stability and peace of product longtime running
Quan Xing.Experiment proves that, it is processed by the invention after material there is good microstructure, can effectively ensure that Al-B4C
Stability and security of the neutron absorber material in the application process of high radioactivity place, with important progressive meaning.
To achieve these goals, the present invention is adopted the following technical scheme that:
A kind of irradiated fuel store and transport Al-B4The heat treatment method of C neutron absorber materials, comprises the following steps:
(1) solution treatment
The material is carried out into solution treatment, solid solubility temperature is 400-650 DEG C, processes 20-240min, obtains part one;
(2) Quenching Treatment
The part one that step 1 is obtained is quenched in being put into water, and water temperature is 10-60 DEG C, obtains part two;
(3) Ageing Treatment
The part two that step 2 is obtained carries out artificial aging treatment, and artificial aging temperature is 100-250 DEG C, artificial aging
Time is 4-30h, is finally air cooled to room temperature, you can;
In the step 2, the time interval that part is quenched in water is transferred to after solution treatment no more than 30s.
Al-B4C neutron absorber materials with aluminium alloy as matrix, with B4C is enhancing phase.
The aluminium alloy is one or more in 2XXX line aluminium alloys, 6XXX line aluminium alloys, 7XXX line aluminium alloys.
In the step 1, solid solubility temperature is 450-550 DEG C, processes 20-150min, obtains part one.
In the step 2, the time interval that part is quenched in water is transferred to after solution treatment no more than 6s.
In the step 3, artificial aging temperature is 150-200 DEG C, and the artificial aging time is 6-20h.
In the step 3, artificial aging treatment is carried out using thermostatical oil liquid furnace.
Further, in step 1, solid solubility temperature is 530 DEG C, and the time is 120min;In step 2,30 DEG C of water temperature, part once
It is 6s that the time interval quenched in water is transferred to after solution treatment;In step 3, artificial aging temperature is 185-195 DEG C, people
Work aging time is 8-10h.
Further, in step 1, solid solubility temperature is 530 DEG C, and the time is 120min;In step 2,30 DEG C of water temperature, part once
It is 6s that the time interval quenched in water is transferred to after solution treatment;In step 3, artificial aging temperature is 155-165 DEG C, people
Work aging time is 17-19h.
For foregoing problems, the present invention is provided at the heat of a kind of irradiated fuel store and transport Al-B4C neutron absorber materials
Reason method.By alternating temperature stress relief annealing Hot rolling to Al-B4C composite carries out hot rolling for after, and the present invention can be used right
Gained Al-B4C neutron absorber materials are heat-treated.The present invention is first to Al-B4C neutron absorber materials carry out solution treatment, Gu
Solubility temperature is 400-650 DEG C, processes 20-240min, obtains part one.Applicants experimentally found that, when solid solubility temperature is higher than this
During the temperature of invention, a small amount of AlB can be generated2And Al3BC thing phases, its content increases with the rising of temperature.Again will be through solid solution
Part one after treatment is quenched in being put into water, and water temperature is 10-60 DEG C, obtains part two.Finally, the part two for obtaining is carried out
Artificial aging treatment, artificial aging temperature is 100-250 DEG C, and the artificial aging time is 4-30h, and last air is cooled to room temperature,
.
In the present invention, with by the Al-B after hot rolling or hot extrusion4C neutron absorber materials are raw material, by the present invention
Heat treatment method, can further improve B4The distributing homogeneity of C ceramic particles, makes it obtain combination property higher, protects
Demonstrate,prove the stability and security of product longtime running.At present, both at home and abroad to Al-B4The research of C composite shielding materials is mainly concentrated
In preparation method, especially powder metallurgic method and mechanical agitation casting, and the present invention proposes a kind of new heat treatment method,
Al-B can be effectively improved by the method4The performance of C neutron absorber materials, with remarkable progress.
Test result indicate that, the present invention can effectively improve B4Distributing homogeneity of the C particles in aluminum substrate, improves compound
The dimensional stability and comprehensive mechanical property of material, are Al-B4The industrialization production of C neutron absorber materials provides theoretical foundation
And technological guidance, it is a kind of efficient, feasible heat treatment method, for Al-B4The improvement of C neutron absorber material performances has weight
The progressive meaning wanted.
Al-B after processed by the invention4C neutron absorber materials have chemical stability very high, with many potential
Application field, such as:Lightweight structural material, cutting tool, high-abrasive material, reactor irradiated fuel store container, spentnuclear fuel transport are held
The fields such as device, Spent fuel pit screen work, shock resistance structure material, turbine engine components.
In sum, the present invention is for irradiated fuel store and the Al-B of transport4The heat treatment of C composite, after treatment
The comprehensive mechanical property of material is increased substantially, and the stability and use peace run during product long service can be effectively ensured
Quan Xing, for the development in corresponding field, has great importance.
Specific embodiment
All features disclosed in this specification, or disclosed all methods or during the step of, except mutually exclusive
Feature and/or step beyond, can combine by any way.
Any feature disclosed in this specification, unless specifically stated otherwise, can be equivalent or with similar purpose by other
Alternative features are replaced.I.e., unless specifically stated otherwise, each feature is an example in a series of equivalent or similar characteristics
.
Comparative example 1
This example selects Al-20wt%B4C composite, material average thickness 3.0mm, using 2024 aluminium alloys as base
Body.
Wherein, the composition of aluminium alloy is:Si 0.5wt%, Fe 0.2wt%, Cu 4.0wt%, Mn 0.4wt%, Mg
1.5%, Cr≤0.1wt%, Zn≤0.15wt%, Ti≤0.1wt%, inevitable impurity content≤0.1wt% are balance of
Al。
2024Al-20wt%B is obtained by alternating temperature stress relief annealing rolling technique4C shielding composites, do not carry out hot place
Reason.
Comparative example 2
This example selects Al-31%B4C composite, material average thickness 3.0mm, using 2024 aluminium alloys as matrix.
Wherein, the composition of aluminium alloy is:Si 0.4wt%, Fe 0.3wt%, Cu 4.2wt%, Mn 0.5wt%, Mg
1.5%, Cr≤0.1wt%, Zn≤0.15wt%, Ti≤0.1wt%, inevitable impurity content≤0.1wt% are balance of
Al。
2024Al-31wt%B is obtained by alternating temperature stress relief annealing rolling technique4C shielding composites, do not carry out hot place
Reason.
Comparative example 3
This example selects Al-20wt%B4C composite, material average thickness 3.0mm, using 6061 aluminium alloys as base
Body.
Wherein, the composition of aluminium alloy is:Si 0.7wt%, Fe 0.2wt%, Cu 0.3wt%, Mn 0.1wt%, Mg
1.0%, Cr≤0.1wt%, Zn≤0.15wt%, Ti≤0.15wt%, inevitable impurity content≤0.1wt%, surplus
It is Al.
6061Al-20wt%B is obtained by alternating temperature stress relief annealing rolling technique4C shielding composites, do not carry out hot place
Reason.
Comparative example 4
This example selects Al-31wt%B4C composite, material average thickness 3.0mm, using 6061 aluminium alloys as base
Body.
Wherein, the composition of aluminium alloy is:Si 0.7wt%, Fe 0.5wt%, Cu 0.2wt%, Mn 0.4wt%, Mg
1.1wt%, Cr≤0.1wt%, Zn≤0.15wt%, Ti≤0.15wt%, inevitable impurity content≤0.15wt% are remaining
It is Al to measure.
6061Al-31wt%B is obtained by alternating temperature stress relief annealing rolling technique4C shielding composites, do not carry out hot place
Reason.
Comparative example 5
This example selects Al-31wt%B4C composite, material average thickness 3.0mm, using 6351 aluminium alloys as base
Body.
Wherein, the composition of aluminium alloy is:Si 1.0wt%, Fe 0.1wt%, Cu 0.1wt%, Mn 0.4wt%, Mg
0.5%, Zn≤0.15wt%, Ti≤0.1wt%, inevitable impurity content≤0.1wt%, balance of Al.
6351Al-31wt%B is obtained by alternating temperature stress relief annealing rolling technique4C shielding composites, do not carry out hot place
Reason.
Comparative example 6
This example selects Al-31wt%B4C composite, material average thickness 3.0mm, using 7075 aluminium alloys as base
Body.
Wherein, the composition of aluminium alloy is:Si 0.40wt%, Fe 0.50wt%, Cu 1.70wt%, Mn 0.30wt%,
Mg 2.7wt%, Ti, 0.20wt%, Zn 5.1-6.1wt%, inevitable impurity content≤0.1wt%, balance of Al.
6351Al-31wt%B is obtained by alternating temperature stress relief annealing rolling technique4C shielding composites, do not carry out hot place
Reason.
Embodiment 1
The present embodiment selects Al-20wt%B4C composite, using 2024 aluminium alloys as matrix, alloying component is with contrast
Example 1.Material average thickness 3.0mm.
The material is heat-treated, processing procedure is as follows:By the Al-20wt%B of rolled4C composite is put into case
In formula heat-treatment furnace, solution treatment is carried out, 535 ± 5 DEG C of solid solubility temperature, solution time 120min obtains part one;Then by portion
Part one is put into water carries out Quenching Treatment, 20 DEG C of water temperature, and the time that Quenching Treatment process is transferred to from solution treatment is 5s, obtains portion
Part two;Part two is finally carried out into Ageing Treatment, 190 DEG C of artificial aging temperature, aging time 9h.
After measured:2024Al-20wt%B after heat treatment4The micro-vickers hardness of C shielding composites is carried by 104
Up to 127, tensile strength is improved to 322MPa by 302MPa.
Embodiment 2
The present embodiment selects Al-31%B4C composite, using 2024 aluminium alloys as matrix, the same comparative example of alloying component
2.Material average thickness 3.0mm.
The material is heat-treated, processing procedure is as follows:By the Al-31%B of rolled4C composite is put into box
In heat-treatment furnace, solution treatment is carried out, 535 ± 5 DEG C of solid solubility temperature, solution time 120min obtains part one;Then by part
One is put into water and carries out Quenching Treatment, 30 DEG C of water temperature, and the time that Quenching Treatment process is transferred to from solution treatment is 5s, obtains part
Two;Part two is finally carried out into Ageing Treatment, 192 DEG C of artificial aging temperature, aging time 12h.
After measured:2024Al-31%B after heat treatment4The micro-vickers hardness of C shielding composites is improved by 125
To 141, tensile strength is improved to 337MPa by 328MPa.
Embodiment 3
The present embodiment selects Al-20wt%B4C composite, using 6061 aluminium alloys as matrix, alloying component is with contrast
Example 3.Material average thickness 3.0mm.
The material is heat-treated, processing procedure is as follows:By the Al-B of rolled4C composite is put at box heat
In reason stove, solution treatment is carried out, 530 ± 3 DEG C of solid solubility temperature, solution time 120min obtains part one;Then part one is put
Enter and carry out in water Quenching Treatment, 25 DEG C of water temperature, the time that solution treatment is transferred to Quenching Treatment process is 5s, obtains part two;Most
Part two is carried out into Ageing Treatment, 160 DEG C of artificial aging temperature, aging time 18h afterwards.
During solid solution, Mg can be formed in alloy matrix aluminum2Si phases, can be solid-solubilized in aluminium alloy under condition of heat treatment
In matrix, so that Al-B4C composite has the ability of artificial age-hardening.After measured:6061Al- after heat treatment
20wt%B4The micro-vickers hardness of C composite shielding materials is improved to 146 by 127, tensile strength by 224MPa improve to
278MPa。
Embodiment 4
The present embodiment selects Al-31wt%B4C composite, using 6061 aluminium alloys as matrix, alloying component is with contrast
Example 4.Material average thickness 3.0mm.
The material is heat-treated, processing procedure is as follows:By the Al-B of rolled4C composite is put at box heat
In reason stove, solution treatment is carried out, 530 ± 3 DEG C of solid solubility temperature, solution time 120min obtains part one;Then part one is put
Enter and carry out in water Quenching Treatment, 28 DEG C of water temperature, the time that Quenching Treatment process is transferred to from solution treatment is 5s, obtains part two;
Part two is finally carried out into Ageing Treatment, 165 DEG C of artificial aging temperature, aging time 17h.It is GP in the process of artificial aging
Area --- needle-like Mg2Si non-equilibrium phases --- bar-shaped Mg2Si non-equilibrium phases --- sheet Mg2Si non-equilibrium phases, so as to reach timeliness
Effect.
After measured:6061Al-31wt%B after heat treatment4The micro-vickers hardness of C composite shielding materials is carried by 143
Up to 178, tensile strength is improved to 309MPa by 279MPa.
Embodiment 5
The present embodiment selects Al-31wt%B4C composite, using 6351 aluminium alloys as matrix, alloying component is with contrast
Example 5.Material average thickness 3.0mm.
The process processed the material is as follows:First by the Al-B of rolled4C composite is put into annealing furnace
Row annealing, 350 DEG C of annealing temperature, annealing time 4h;Then carry out solution treatment, 505 DEG C of solid solubility temperature, solution time 90min,
Obtain part one;Then part one is put into carries out Quenching Treatment in water, 25 DEG C of water temperature is transferred to Quenching Treatment from solution treatment
The time of process is 5s, obtains part two;Part two is finally carried out into Ageing Treatment, 170 DEG C of artificial aging temperature, aging time
6h。
After measured:6351Al-31wt%B after heat treatment4The micro-vickers hardness of C composite shielding materials is carried by 112
Up to 127, tensile strength is improved to 301MPa by 282MPa.
Example 6
The present embodiment selects Al-31wt%B4C composite, using 7075 aluminium alloys as matrix, alloying component is with contrast
Example 6.Material average thickness 3.0mm.
The material is heat-treated, processing procedure is as follows:First by the Al-B of rolled4C composite is put into hot place
In reason stove, solution treatment is carried out, solid solubility temperature is 520 ± 3 DEG C, and solution time 90min obtains part one;Then by part one
Being put into water carries out Quenching Treatment, 35 DEG C of water temperature, and the time that Quenching Treatment process is transferred to from solution treatment is 6s, obtains part
Two;Part two is finally carried out into Ageing Treatment, 175 DEG C of artificial aging temperature, aging time 12h.
After measured:7075Al-31wt%B after heat treatment4The micro-vickers hardness of C composite shielding materials is carried by 153
Up to 176, tensile strength is improved to 595MPa by 576MPa.
Corresponding measurement result is as shown in table 1 below.
The mechanics performance determining result of the comparative example of table 1 and embodiment
Sample | Hardness/HV | Yield strength/MPa | Tensile strength/MPa |
Comparative example 1 | 104 | 260 | 302 |
Embodiment 1 | 127 | 295 | 322 |
Comparative example 2 | 125 | 308 | 328 |
Embodiment 2 | 141 | 312 | 337 |
Comparative example 3 | 127 | 198 | 224 |
Embodiment 3 | 146 | 249 | 278 |
Comparative example 4 | 143 | 229 | 279 |
Embodiment 4 | 178 | 260 | 309 |
Comparative example 5 | 112 | 258 | 282 |
Embodiment 5 | 127 | 270 | 301 |
Comparative example 6 | 153 | 501 | 576 |
Embodiment 6 | 176 | 524 | 595 |
Table 1 test result indicate that:Through embodiment 1, embodiment 2, embodiment 3, embodiment 4, embodiment 5, the heat of example 6
After treatment, the combination property of material is obtained for raising.The present invention passes through between solution treatment, Quenching Treatment, Ageing Treatment
Cooperate, Al-B can be significantly improved4The mechanical property of C metal-base composites.In identical B4During C ceramic particle contents, this
Invention can be obviously improved the hardness and mechanical property of composite, and this is conducive to the steady of neutron absorber material product longtime running
Qualitative and safety in utilization.Flow of the present invention is simple, and production equipment requirement is low, it is easy to accomplish industrial mass processes product, institute
The product stability of preparation and safe, with preferable application prospect.
The above is only concrete application example of the invention, for explaining the present invention, protection scope of the present invention is not constituted
Any limitation.All use equivalence replacements or improvement, the technical scheme retouched and formed, are accordingly to be regarded as rights protection scope of the present invention
Within.The invention is not limited in foregoing specific embodiment.The present invention expand to it is any disclose in this manual it is new
Feature or any new combination, and disclose any new method or process the step of or any new combination.
Claims (5)
1. a kind of irradiated fuel store and transport Al-B4The heat treatment method of C neutron absorber materials, it is characterised in that including as follows
Step:
(1)Solution treatment
The material is carried out into solution treatment, solid solubility temperature is 400-650 DEG C, processes 20-240min, obtains part one;
(2)Quenching Treatment
The part one that step 1 is obtained is quenched in being put into water, and water temperature is 10-60 DEG C, obtains part two;
(3)Ageing Treatment
The part two that step 2 is obtained carries out artificial aging treatment, and artificial aging temperature is 150-200 DEG C, artificial aging time
It is 6-20h, is finally air cooled to room temperature, you can;
Al-B4C neutron absorber materials with aluminium alloy as matrix, with B4C is enhancing phase;
The aluminium alloy is one or more in 2XXX line aluminium alloys, 6XXX line aluminium alloys, 7XXX line aluminium alloys;
In the step 2, the time interval that part is quenched in water is transferred to after solution treatment no more than 6s.
2. irradiated fuel store and transport Al-B according to claim 14The heat treatment method of C neutron absorber materials, its feature
It is that in the step 1, solid solubility temperature is 450-550 DEG C, processes 20-150min, obtains part one.
3. irradiated fuel store and transport Al-B according to claim 14The heat treatment method of C neutron absorber materials, its feature
It is in the step 3, artificial aging treatment to be carried out using thermostatical oil liquid furnace.
4. irradiated fuel store and transport Al-B according to claim any one of 1-34The heat treatment side of C neutron absorber materials
Method, it is characterised in that in step 1, solid solubility temperature is 530 DEG C, and the time is 120min;In step 2,30 DEG C of water temperature, part once
It is 6s that the time interval quenched in water is transferred to after solution treatment;In step 3, artificial aging temperature is 185-195 DEG C, people
Work aging time is 8-10h.
5. irradiated fuel store and transport Al-B according to claim any one of 1-34The heat treatment side of C neutron absorber materials
Method, it is characterised in that in step 1, solid solubility temperature is 530 DEG C, and the time is 120min;In step 2,30 DEG C of water temperature, part once
It is 6s that the time interval quenched in water is transferred to after solution treatment;In step 3, artificial aging temperature is 155-165 DEG C, people
Work aging time is 17-19h.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201510062108.8A CN104611653B (en) | 2015-02-06 | 2015-02-06 | Al B are used in a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
CN201510062108.8A CN104611653B (en) | 2015-02-06 | 2015-02-06 | Al B are used in a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials |
Publications (2)
Publication Number | Publication Date |
---|---|
CN104611653A CN104611653A (en) | 2015-05-13 |
CN104611653B true CN104611653B (en) | 2017-06-09 |
Family
ID=53146292
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
CN201510062108.8A Expired - Fee Related CN104611653B (en) | 2015-02-06 | 2015-02-06 | Al B are used in a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials |
Country Status (1)
Country | Link |
---|---|
CN (1) | CN104611653B (en) |
Families Citing this family (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN113151763A (en) * | 2021-03-23 | 2021-07-23 | 西安稀有金属材料研究院有限公司 | Heat treatment method of boron-tungsten-aluminum composite shielding material |
Family Cites Families (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN103572087B (en) * | 2013-11-25 | 2015-12-09 | 武汉理工大学 | The preparation method of boron carbide particles reinforced aluminum matrix composites |
-
2015
- 2015-02-06 CN CN201510062108.8A patent/CN104611653B/en not_active Expired - Fee Related
Also Published As
Publication number | Publication date |
---|---|
CN104611653A (en) | 2015-05-13 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
CN106987780B (en) | A kind of nuclear reactor involucrum FeCrAl base alloy material and preparation method thereof | |
Choi et al. | Fabrication of Gd containing duplex stainless steel sheet for neutron absorbing structural materials | |
CN104946911B (en) | A kind of spent fuel storage rack high-volume fractional B4The preparation method of C/Al composite | |
CN110396624B (en) | Boron-rich nickel-tungsten-based alloy material for nuclear shielding and preparation method thereof | |
CN102268582A (en) | Alumina-based material with comprehensive shielding effect of rays and neutrons | |
CN106995902B (en) | A kind of FeCrAl based alloy cladding materials and preparation method thereof | |
CN110373573B (en) | Gadolinium-rich nickel-tungsten-based alloy material for nuclear shielding and preparation method thereof | |
CN110643859A (en) | Aluminum-based composite material containing gadolinium-tungsten element and application thereof | |
CN110273085B (en) | Gadolinium-rich nickel-based alloy material for reactor spent fuel storage and preparation method thereof | |
CN104611653B (en) | Al B are used in a kind of irradiated fuel store and transport4The heat treatment method of C neutron absorber materials | |
CN107217197B (en) | A kind of advanced Reactor fuel element cladding FeCrAl base alloy material and preparation method thereof | |
Kim et al. | Synthesis and characteristics of ternary Be–Ti–V beryllide pebbles as advanced neutron multipliers | |
CN101476057B (en) | High strength lead alloy and manufacturing method thereof | |
RU2325459C2 (en) | Chromium low-doped corrosion-resistant and radiation-resistant steel | |
CN116288047A (en) | Gadolinium-enriched iron-nickel base alloy material with excellent hot workability for nuclear shielding and preparation method thereof | |
CN107236904B (en) | A kind of nuclear reactor FeCrAl base alloy material and preparation method thereof | |
CN115418530A (en) | Dysprosium-rich nickel-tungsten alloy material for nuclear shielding and preparation method thereof | |
CN115011839A (en) | Titanium-gadolinium alloy material for nuclear shielding, and preparation method and application thereof | |
CN110408818A (en) | One seed nucleus irradiated fuel store B4Cp/ Al neutron absorber material and preparation method thereof | |
Baik et al. | Effect of gadolinium addition on the corrosion, wear, and neutron absorbing behaviors of duplex stainless steel sheet | |
CN115449668A (en) | Preparation method of dysprosium-rich nickel-based alloy for nuclear shielding material | |
Moczygemba et al. | Structure characterization and steam oxidation performance of U3Si2 with Zr alloying additions | |
Malik et al. | The system Ce–Zn–B at 800° C | |
IE861851L (en) | Absorber for nuclear radiations | |
CN107142424B (en) | A kind of nuclear reactor structure material FeCrAl base alloy material and preparation method thereof |
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 | ||
CF01 | Termination of patent right due to non-payment of annual fee |
Granted publication date: 20170609 |
|
CF01 | Termination of patent right due to non-payment of annual fee |