CN106987780A - A kind of nuclear reactor involucrum FeCrAl base alloy materials and preparation method thereof - Google Patents
A kind of nuclear reactor involucrum FeCrAl base alloy materials and preparation method thereof Download PDFInfo
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- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
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- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/06—Ferrous alloys, e.g. steel alloys containing aluminium
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- C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
- C21D1/00—General methods or devices for heat treatment, e.g. annealing, hardening, quenching or tempering
- C21D1/26—Methods of annealing
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- C21D6/002—Heat treatment of ferrous alloys containing Cr
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- C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
- C21D6/00—Heat treatment of ferrous alloys
- C21D6/005—Heat treatment of ferrous alloys containing Mn
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- C21D6/00—Heat treatment of ferrous alloys
- C21D6/008—Heat treatment of ferrous alloys containing Si
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- C21D—MODIFYING THE PHYSICAL STRUCTURE OF FERROUS METALS; GENERAL DEVICES FOR HEAT TREATMENT OF FERROUS OR NON-FERROUS METALS OR ALLOYS; MAKING METAL MALLEABLE, e.g. BY DECARBURISATION OR TEMPERING
- C21D8/00—Modifying the physical properties by deformation combined with, or followed by, heat treatment
- C21D8/02—Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips
- C21D8/0221—Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips characterised by the working steps
- C21D8/0226—Hot rolling
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- C21D8/00—Modifying the physical properties by deformation combined with, or followed by, heat treatment
- C21D8/02—Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips
- C21D8/0247—Modifying the physical properties by deformation combined with, or followed by, heat treatment during manufacturing of plates or strips characterised by the heat treatment
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- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
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- C22C38/00—Ferrous alloys, e.g. steel alloys
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- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/04—Ferrous alloys, e.g. steel alloys containing manganese
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- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/22—Ferrous alloys, e.g. steel alloys containing chromium with molybdenum or tungsten
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- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/26—Ferrous alloys, e.g. steel alloys containing chromium with niobium or tantalum
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C38/00—Ferrous alloys, e.g. steel alloys
- C22C38/18—Ferrous alloys, e.g. steel alloys containing chromium
- C22C38/28—Ferrous alloys, e.g. steel alloys containing chromium with titanium or zirconium
Abstract
The invention discloses a kind of nuclear reactor involucrum FeCrAl base alloy materials, by weight, Cr：12.5~14.5%, Al：3.5~5.5%, Mo：2~3.5%, Nb：1~2.5%, Si：0.1~0.5%, Zr：0~0.5%, Mn：0~0.05%, La+Ce or La+Y：0.01~0.1%, surplus is iron and the impurity for meeting industrial standard.The alloy material of the present invention has excellent high temperature oxidation resistance under 1000 DEG C of water vapor conditions, and alloy has higher elevated temperature strength and thermal structure stability under 800 DEG C of high temperature, at room temperature with very high mechanical strength and higher plasticity and toughness.
Description
Technical field
The invention belongs to fe-based alloy structure material and specialty alloy materials technical field, and in particular to for pressing water to react
A kind of nuclear reactor involucrum FeCrAl base alloy materials and preparation method thereof in heap.
Background technology
Fuel element is the core component of power producer reactor core, and its performance is directly connected to the peace of nuclear reactor operation
Full property and economy.Zircaloy is that current commercial nuclear power light water reactor fuel element uniquely uses cladding materials.But in emergency case
Under (such as Fukushima, Japan nuclear accident, presurized water reactor loss of-coolant accident (LOCA)), zirconium alloy cladding and high temperature coolant water vigorous reaction release big
Calorimetric and explosion gas hydrogen, cause cladding materials mechanical property to deteriorate, produce reactor hydrogen it is quick-fried with a large amount of radioactive products outside
The nuclear catastrophe consequence such as let out.So, of future generation and following advanced nuclear power presurized water reactor is with can material and now uses nuclear power
Zirconium alloy cladding material is compared, it is necessary to possess more preferable high temperature resistance steam oxidation ability, elevated temperature strength and high-temperature stability, energy
It is enough that bigger safe clearance is provided within a certain period of time and avoids potential serious reactor core from melting accident, also referred to as crash-proof involucrum
Material.
Crash-proof cladding materials require its can in 800-1000 DEG C or so steam ambient in several hours (time it is more long more
Good, rescue time can be increased) a very low oxidation rate (2 orders of magnitude at least lower than zircaloy) is kept, while the involucrum
Material has the mechanical strength for meeting short cycle reliability for (>=800 DEG C) under the high temperature conditions, so just can be more than design
The safety allowance of reactor core accident is improved when basic accident.Under the promotion of this tight demand background, world nuclear big country pair
Many candidate's crash-proof cladding materials have carried out substantial amounts of HIGH TEMPERATURE OXIDATION PERFORMANCE, most represent include Zr-2, Zr-4,
The materials such as SiC, 304SS, 310SS, FeCrAl based alloy.Result of study shows：FeCrAl based alloys with good due to resisting
Irradiation behaviour, and the FeCrAl alloys containing appropriate amount Cr, Al oxidation-resistance property be far superior to Zr-2, Zr-4,
304SS, 310SS alloy, its high temperature oxidation resistance and the SiC material prepared using CVD method are substantially suitable, become elder generation
Enter in the research and development of nuclear power crash-proof cladding materials and extremely have potential cladding materials.
The high temperature oxidation resistance of commercialization FeCrAl base alloy materials is more notable mostly at present, but in reactor operation work
Hardening and brittle degree are serious under condition heat aging and radiation parameter, and major safety risks are brought to reactor operation.Moreover,
Commercial FeCrAl based alloy room temperature mechanics plasticity is poor, causes sheet alloy and thin-wall pipes processing difficulties, it is impossible to meet
Industrialize actual demand.
The content of the invention
The technical problems to be solved by the invention are to provide a kind of nuclear reactor involucrum FeCrAl base alloy materials, should
Alloy material has excellent high temperature oxidation resistance under 1000 DEG C of water vapor conditions, and alloy has higher under 800 DEG C of high temperature
Elevated temperature strength and thermal structure stability, at room temperature with very high mechanical strength and higher plasticity and toughness.Also disclose one
Plant preparation method.
The present invention is achieved through the following technical solutions：
A kind of nuclear reactor involucrum FeCrAl base alloy materials, by weight, Cr：12.5~14.5%, Al：3.5~
5.5%, Mo：2~3.5%, Nb：1~2.5%, Si：0.1~0.5%, Zr：0~0.5%, Mn：0-0.05%, La+Ce or La
+Y：0.01~0.1%, surplus is iron and the impurity for meeting industrial standard.
By weight, Cr：13%, Al：3.5%, Mo：3.0%, Nb：2.5%, Si：0.12%, Zr：0.1%, Mn：
0%, La+Ce：0.1%, surplus is iron and the impurity for meeting industrial standard.
Mo, Nb, Zr total weight percent content >=3.5%.
Cr, Al and Si total weight percent content >=16.5%.
C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%.
The preparation method of foregoing advanced Reactor fuel element cladding FeCrAl base alloy materials, it is characterised in that
Specifically include following steps：Melting ingot casting, ingot casting is annealed, forged, is heat-treated, hot rolling, heat aging processing, it is cold rolling；
Soaking time >=3h after annealing temperature >=1150 DEG C, annealing；
Forging includes begin forging and finish-forging, initial forging temperature >=1050 DEG C, final forging temperature >=850 DEG C；
Thermal treatment rate is：780 DEG C~800 DEG C/0.5-1.0h；
Hot-rolled temperature is≤850 DEG C, deflection >=65% of processed material during hot rolling；
The aging temp of heat aging processing is 700 DEG C~800 DEG C, and aging time is：20h~100h；
Intermediate anneal temperature and final annealing temperature≤750 DEG C in cold-rolled process, processed material deflection when cold rolling
>=30%.
Need to remove the oxide skin on ingot casting surface before forging and cleaning treatment is carried out to ingot casting surface.
Need to remove the table for being forged the surface scale of processing material and being forged it processing material before heat treatment
Face carries out cleaning treatment.
Forging ratio is more than 2 during forging.
The setting of temperature in hot rolling and cold-rolled process, effectively prevent Laves second phase particles processing and it is heat treated
Growing up in journey, obtains tiny second phase particles, it is ensured that the high temperature oxidation resistance of alloy, while enhancing room temperature and high temperature
Strengthen effect.
Inventor has found that existing most commercial FeCrAl base alloy materials have significant high temperature resistance oxygen in practice process
Change performance, but hardening and brittle degree are serious under reactor operation operating mode heat aging and radiation parameter, and FeCrAl bases are closed
Golden room temperature mechanics plasticity is poor, causes sheet alloy and thin-wall pipes processing difficulties, and its reason is：Cr, Al content are too high.For
Prevent FeCrAl based alloys harden and brittle tendency aggravation, cause alloy to be interrupted in reactor operation and processing preparation process
Split, the present invention carries out creative component to Cr, Al, Mo, Nb, Si, Zr, Mn, La, Ce etc. and matched, one side Cr, Al and Si's
Effectively coordinate, can effectively reduce oxidation rate of the alloy material of the present invention under the conditions of 800-1000 DEG C so that the present invention is closed
The oxidation rate of golden material is maintained at a relatively low level, and oxidation rate speedup is slow, it is ensured that FeCrAl base alloy materials have
There is high temperature oxidation resistance, another aspect Mo, Nb, Zr effective cooperation can separate out the Laves second phase particles of a large amount of disperses,
Crystal grain thinning simultaneously improves Alloy At Room Temperature mechanical property and elevated temperature strength, and La+Ce or La+Y being capable of softener materials, raising material sheet
The plasticity and toughness of body so that the structure stability of alloy material under the high temperature conditions is substantially improved.In general, alloy material
Intensity and toughness be conflict, generally improve intensity, toughness will be reduced, or toughness is improved, intensity just reduces.Exactly
The present invention on Cr, Al and Si combination foundation, is being ensured using Mo, Nb, Zr combination and La+Ce or La+Y combination collocation
On the basis of certain high temperature oxidation resistance, it can both ensure the intensity of alloy material, and will not also reduce the modeling of alloy material
Toughness, assigns the excellent mechanical property of this alloy material and plasticity and toughness energy.
The present invention compared with prior art, has the following advantages and advantages：
1st, alloy material of the invention can have the alloy under 800 DEG C of high temperature to have on the basis of high-temperature oxidation resistant
Higher elevated temperature strength and thermal structure stability, at room temperature with very high mechanical strength and higher plasticity and toughness；
2nd, alloy of the present invention has very excellent high temperature oxidation resistance, high-temperature steam under 1000 DEG C of water vapor conditions
Oxidation rate is well below current commercial nuclear power cladding materials Zr-4 alloys；
3rd, alloy of the present invention obtains small and dispersed distribution after being processed through zerolling, long-time timeliness and Technology for Heating Processing
The phases of Laves second, significantly improve alloy mechanical property (room temperature obdurability and elevated temperature strength) and alloy structure heat it is steady
It is qualitative.
Embodiment
For the object, technical solutions and advantages of the present invention are more clearly understood, with reference to embodiment, to present invention work
Further to describe in detail, exemplary embodiment and its explanation of the invention is only used for explaining the present invention, is not intended as to this
The restriction of invention.
Embodiment
The composition proportion of the FeCrAl based alloys embodiment of the present invention of table 1 (remainder is iron)
The preparation method that identical (i.e. parameter is identical) is passed through with 1-7# alloy material proportioning：It is foregoing advanced
The Reactor fuel element cladding preparation method of FeCrAl base alloy materials, specifically includes following steps：
(1) high purity alloys for being more than 99.9% with ingot iron and purity press table 1 and are formulated dispensing, use vacuum induction melting furnace
Melting prepares 20~30 kilograms of ingot castings；
(2) above-mentioned ingot casting is subjected to high temperature homogenizing annealing temperature.Annealing temperature is：>=1150 DEG C, soaking time >=3h；
(3) surface scale of ingot casting after homogenizing annealing is removed, high temperature forging is carried out after surface cleaning is handled, forging of beginning
Temperature is：>=1050 DEG C, final forging temperature is：>=850 DEG C, forging ratio >=2；
(4) surface scale of sheet material after forging is removed, the sheet material after surface cleaning is handled is heat-treated, and is heat-treated
System is：780~800 DEG C/0.5~1h.It is heat-treated the hot rolling of laggard andante material, hot-rolled temperature≤850 DEG C, material deflection >=
50%；
(5) sheet material after hot rolling is subjected to heat aging processing, specific aging temp is：700 DEG C~800 DEG C, aging time
For：20h~100h；
(6) hot rolled plate after heat aging is handled carries out cold rolling, intermediate anneal temperature in cold-rolled process and most retreats
Fiery temperature≤750 DEG C, cold rolling reduction >=30%；
For the advance for the formula for further illustrating the present invention, the present invention uses embodiment based on optimal case 6#,
The ratio beyond contrast test, the selection scope of the invention is carried out on the basis of 6# and carries out contrast test：The preparation of all comparative examples
Method is all identical with 6#.
Comparative example 1*：Only add Cr, Al, Si, Mo, and composition is identical with 6#；
Comparative example 2*：Only add Cr, Al, Si, Nb, and composition is identical with 6#；
Comparative example 3*：Only add Cr, Al, Si, Zr, and composition is identical with 6#；
Comparative example 4*：Only add Cr, Al, Si, Mo, La+Ce, and composition is identical with 6#；
Comparative example 5*：Only add Cr, Al, Si, Nb, La+Ce, and composition is identical with 6#；
Comparative example 6*：Raw material is identical with 6#, and the content that the content that Mo content is 1%, Nb is 0.5%, Zr is 1%, La+
Ce content is 0.15%, and remaining composition is consistent with 6#；
Comparative example 7*：Raw material is identical with 6#, and the content that the content that Mo content is 4%, Nb is 2.6%, Zr is 2%, La+
Ce content is 0.2%, and remaining composition is consistent with 6#；
Comparative example 8*：Cr contents are that 12%, Al content is that 3%, Si contents are 0.08%, remaining composition and comparative example 7* phases
Together；
Comparative example 9*：Cr contents are that 15%, Al content is that 5.9%, Si contents are 0.8%, remaining composition and comparative example 7*
It is identical.
The FeCrAl based alloys comparative example proportioning of the present invention of table 2 (remainder is iron)
Alloy material prepared by embodiment 1#-7# and comparative example 1*-9* carries out the test of mechanical property and plasticity and toughness, its
Test result such as table 3 below,
As can be seen from the above table, embodiment 1-2# alloy material is under the conditions of basic components are only met, although have
Certain high temperature oxidation resistance, but its overall synthetic performance is not so good as to meet the good of 3-7# alloy material.(3-7# is simultaneously full
Sufficient Mo, Nb, Zr total weight percent content >=3.5%；Cr, Al and Si total weight percent content >=16.5%)
In the case that embodiment 6# and comparative example 1-5*, Cr, Al and Si content are constant, arbitrarily single plus Mo, Nb,
Zr, Mo, La+Ce, the combination property of alloy material are poor.
From embodiment 6# and comparative example 6-9*, Cr, Al and Si, Mo, Nb, Mo, La+Ce outside the scope of the present invention
Any combination, the combination property of alloy material is also good without embodiment.
It is worth noting that, the performance evaluation of FeCrAl base alloy materials is the fastidious process of a synthesis, single number
Height to its performance quality judge do not have decisive significance, those skilled in the art evaluate FeCrAl base alloy materials
Performance when, high temperature oxidation resistance should be considered, while also needing to consider the size of its toughness and strength values, such as anti-height
But its low toughness of warm oxidation susceptibility and intensity can not reach and apply level, and for example toughness is strong, its intensity is not high, with upper
The FeCrAl base alloy materials of performance are stated not for needed for application, not in the category of the excellent identification of combination property.
Above-described embodiment, has been carried out further to the purpose of the present invention, technical scheme and beneficial effect
Describe in detail, should be understood that the embodiment that the foregoing is only the present invention, be not intended to limit the present invention
Protection domain, within the spirit and principles of the invention, any modification, equivalent substitution and improvements done etc. all should be included
Within protection scope of the present invention.
Claims (9)
1. a kind of nuclear reactor involucrum FeCrAl base alloy materials, it is characterised in that by weight, Cr：12.5~14.5%,
Al：3.5~5.5%, Mo：2~3.5%, Nb：1~2.5%, Si：0.1~0.5%, Zr：0~0.5%, Mn：0~0.05%,
La+Ce or La+Y：0.01~0.1%, surplus is iron and the impurity for meeting industrial standard.
2. nuclear reactor involucrum FeCrAl base alloy materials according to claim 1, it is characterised in that by weight,
Cr：13%, Al：3.5%, Mo：3.0%, Nb：2.5%, Si：0.12%, Zr：0.1%, Mn：0%, La+Ce：0.1%, surplus
For iron and the impurity for meeting industrial standard.
3. nuclear reactor involucrum FeCrAl base alloy materials according to claim 1 or 2, it is characterised in that Mo, Nb,
Zr total weight percent content >=3.5%.
4. nuclear reactor involucrum FeCrAl base alloy materials according to claim 1 or 2, it is characterised in that Cr, Al and
Si total weight percent content >=16.5%.
5. nuclear reactor involucrum FeCrAl base alloy materials according to claim 1 or 2, it is characterised in that in impurity,
C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%.
6. the preparation method of the nuclear reactor involucrum FeCrAl base alloy materials according to claim any one of 1-5, its
It is characterised by, specifically includes following steps：Melting ingot casting, ingot casting is annealed, forged, is heat-treated, hot rolling, heat aging processing, it is cold
Roll；
Soaking time >=3h after annealing temperature >=1150 DEG C, annealing；
Forging includes begin forging and finish-forging, initial forging temperature >=1050 DEG C, final forging temperature >=850 DEG C；
Thermal treatment rate is：780 DEG C~800 DEG C/0.5-1.0h；
Hot-rolled temperature is≤850 DEG C, deflection >=65% of processed material during hot rolling；
The aging temp of heat aging processing is 700 DEG C~800 DEG C, and aging time is：20h~100h；
Intermediate anneal temperature and final annealing temperature≤750 DEG C in cold-rolled process, processed material deflection when cold rolling >=
30%.
7. preparation method according to claim 6, it is characterised in that need to remove the oxide skin on ingot casting surface before forging
And cleaning treatment is carried out to ingot casting surface.
8. preparation method according to claim 7, it is characterised in that need removal to be forged processing material before heat treatment
Surface scale and it is forged processing material surface carry out cleaning treatment.
9. preparation method according to claim 7, it is characterised in that forging ratio is more than 2 during forging.
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Cited By (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108165717A (en) * | 2017-12-05 | 2018-06-15 | 中国科学院金属研究所 | A kind of preparation process of nuclear fuel element FeCrAl tubing |
| CN110195191A (en) * | 2019-06-13 | 2019-09-03 | 上海大学 | Nuclear reactor fuel element cladding materials Fe-Cr-Al alloy and preparation method thereof |
| CN111363982A (en) * | 2020-04-08 | 2020-07-03 | 四川大学 | Novel titanium-containing ferrite system heat-resistant steel and preparation method and application thereof |
| CN111826590A (en) * | 2020-06-08 | 2020-10-27 | 东莞材料基因高等理工研究院 | Fe23Zr6And Fe2M-Laves phase co-reinforced FeCrAl stainless steel and preparation method thereof |
| CN115161564A (en) * | 2022-07-12 | 2022-10-11 | 中国核动力研究设计院 | FeCrAl stainless steel cladding tube and preparation method thereof |
| CN117187705A (en) * | 2023-10-27 | 2023-12-08 | 上海交通大学 | Heat treatment method of low-Cr and high-toughness alloy |
Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106381448A (en) * | 2016-10-12 | 2017-02-08 | 苏州热工研究院有限公司 | FeCrAl alloy material for nuclear reactor fuel cladding material |
-
2017
- 2017-05-27 CN CN201710389961.XA patent/CN106987780B/en active Active
Patent Citations (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106381448A (en) * | 2016-10-12 | 2017-02-08 | 苏州热工研究院有限公司 | FeCrAl alloy material for nuclear reactor fuel cladding material |
Non-Patent Citations (2)
| Title |
|---|
| Y. YAMAMOTO等: "Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors", 《JOURNAL OF NUCLEAR MATERIALS》 * |
| Y. YAMAMOTO等: "Letter Report Documenting Progress of Second Generation ATF FeCrAl Alloy Fabrication", 《FCRD ADVANCED FUELS CAMPAIGN (AFC) LEVEL 3 MILESTONE REPORT》 * |
Cited By (10)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108165717A (en) * | 2017-12-05 | 2018-06-15 | 中国科学院金属研究所 | A kind of preparation process of nuclear fuel element FeCrAl tubing |
| CN110195191A (en) * | 2019-06-13 | 2019-09-03 | 上海大学 | Nuclear reactor fuel element cladding materials Fe-Cr-Al alloy and preparation method thereof |
| CN110195191B (en) * | 2019-06-13 | 2021-05-07 | 上海大学 | Fe-Cr-Al alloy for nuclear reactor fuel element cladding material and preparation method thereof |
| CN111363982A (en) * | 2020-04-08 | 2020-07-03 | 四川大学 | Novel titanium-containing ferrite system heat-resistant steel and preparation method and application thereof |
| CN111363982B (en) * | 2020-04-08 | 2021-05-25 | 四川大学 | Titanium-containing ferrite system heat-resistant steel and preparation method and application thereof |
| CN111826590A (en) * | 2020-06-08 | 2020-10-27 | 东莞材料基因高等理工研究院 | Fe23Zr6And Fe2M-Laves phase co-reinforced FeCrAl stainless steel and preparation method thereof |
| CN111826590B (en) * | 2020-06-08 | 2022-07-08 | 东莞材料基因高等理工研究院 | Fe23Zr6And Fe2M-Laves phase co-reinforced FeCrAl stainless steel and preparation method thereof |
| CN115161564A (en) * | 2022-07-12 | 2022-10-11 | 中国核动力研究设计院 | FeCrAl stainless steel cladding tube and preparation method thereof |
| CN117187705A (en) * | 2023-10-27 | 2023-12-08 | 上海交通大学 | Heat treatment method of low-Cr and high-toughness alloy |
| CN117187705B (en) * | 2023-10-27 | 2024-03-26 | 上海交通大学 | Heat treatment method of low-Cr and high-toughness alloy |
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