CN107236904A - A kind of nuclear reactor FeCrAl base alloy materials and preparation method thereof - Google Patents
A kind of nuclear reactor FeCrAl base alloy materials and preparation method thereof Download PDFInfo
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Abstract
The invention discloses a kind of nuclear reactor FeCrAl base alloy materials and preparation method thereof, weight percentage, it is composed of the following components, Cr, AI, Mo, Nb, W, Ta, Zr, Ga, Mn, Ce, C, N, O, Fe, impurity, wherein, the total weight percent of Cr, AI alloying element is more than or equal to 17%, and the total weight percent of Cr alloying elements is more than or equal to 12.7%, it is less than or equal to 2.0% that the total weight percent content of Mo, Nb, W, Ta, Zr alloying element, which is more than or equal to 3.1%, Mo and the total weight percent sum of W alloy element,.The interphase interaction of alloying element in the FeCrAl based alloys, with excellent high-temperature steam oxidation resistance energy, irradiation behaviour, there is higher elevated temperature strength and thermal structure stability under 800 DEG C of high temperature, and there is higher mechanical strength and the plasticity properly processed at room temperature.
Description
Technical field
The invention belongs to fe-based alloy structure material and specialty alloy materials technical field, a kind of nuclear reactor is specifically referred to
Reactor core FeCrAl base alloy materials and preparation method thereof.
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 requires that it can keep one very in 800-1000 DEG C or so steam ambients in several hours
Low oxidation rate, 2 orders of magnitude at least lower than zircaloy, while the cladding materials is in the case where being not less than 800 DEG C of hot conditions
With the mechanical strength for meeting short cycle reliability, the peace of reactor core accident so can be just improved when more than design basis accident
Full allowance.Under the promotion of this tight demand background, world nuclear big country has been carried out greatly to many candidate's accident cladding materials
The HIGH TEMPERATURE OXIDATION PERFORMANCE of amount, what is most represented includes Zr-2, Zr-4, SiC, 304SS, 310SS, FeCrAl based alloy etc.
Material.
The FeCrAl base alloy materials of commercialization have higher Cr, Al content (Cr mostly mostly at present：15~30%, Al：
6~15%), therefore its high temperature oxidation resistance is more notable.But because containing higher in commercial FeCrAl base alloy materials
Cr, Al content make that it is hardened under reactor operation operating mode thermal effect and radiation parameter and brittle degree is serious, to reactor operation
Bring great potential safety hazard.Moreover, higher Cr, Al content FeCrAl based alloy room temperature mechanics plasticity it is poor, lead
Cause sheet alloy and thin-wall pipes processing difficulties.
Based on this, study and develop a kind of nuclear reactor FeCrAl base alloy materials of design and preparation method thereof.
The content of the invention
It is an object of the invention to：A kind of nuclear reactor FeCrAl base alloy materials are provided, added in the base
Mo, Nb, W, Ta, Zr micro alloying element of special ratios, and Cr, Al content are reduced, solve existing commercial FeCrAl bases
Alloy material is hardened under reactor operation operating mode thermal failure and radiation parameter and embrittlement is serious, and room temperature mechanics plasticity is poor, close
The technical problems such as payment organization heat endurance difference.
Another object of the present invention is to：A kind of preparation method of FeCrAl base alloy materials is provided, passes through pairing gold dollar
The control of cellulose content, processing technology so that the FeCrAl base alloy materials applied to nuclear reactor have higher resist
Elevated temperature strength and structure stability, at room temperature with very high mechanical strength and the plasticity properly processed.
The present invention is achieved through the following technical solutions：
A kind of nuclear reactor FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr, AI, Mo, Nb, W, Ta, Zr, Ga, Mn, Ce, C, N, O, Fe, impurity, wherein, the total weight percent of Cr, AI alloying element is
More than or equal to 17%, and the total weight percent of Cr alloying elements is more than or equal to 12.7%, Mo, Nb, W, Ta, Zr alloying element
It is less than or equal to 2.0% that total weight percent content, which is more than or equal to 3.1%, Mo and the total weight percent sum of W alloy element,.
In order to prevent the hardening of FeCrAl based alloys and the aggravation of brittle tendency, alloy is caused in reactor operation and processing system
It is broken during standby, it should ensureing FeCrAl based alloys with strict control on higher high temperature resistance steam oxidation capability foundation discussion simultaneously
Reduce Cr, AI content.Meanwhile, contain the FeCrAl based alloys of appropriate Cr, AI content as reactor crash-proof fuel can
Materials'use should also have following performance in addition to above-mentioned performance requirement：1) at room temperature alloy have higher-strength and
Plasticity, basis is provided for thin-walled involucrum tubular object extruding；2) it is：(being not less than 800 DEG C) at high temperature, alloy has higher-strength；3)
It is：Alloy high-temp tissue is more stable, as far as possible improve alloy recrystallization temperature so that alloy more than 800 DEG C with compared with
Strong thermal structure stability simultaneously postpones alloy grain size and grown up, and only stable tissue and the crystal grain of refinement can just bring alloy
Enough excellent properties.
Impurity content of the present invention meets the standard of current commercial industrial pure iron and ferritic stainless steel.
FeCrAl based alloys formula of the present invention is the improvement to existing FeCrAl based alloys, on the basis of existing components
On add Mo, Nb, W, Ta, Zr, Ga, Mn, Ce alloying element, while to Cr, Al content is controlled, reduce Cr, Al's
Content, to avoid alloy hardening and brittle tendency.
Applicant is had found by the experiment that studies for a long period of time：Cr, Al content are simply reduced on the basis of existing alloy, although
Alloy hardening and brittle tendency can be avoided, but the high temperature resistance steam oxidation ability of alloy is reduced, and elevated temperature strength and toughness
It is bad.By adding after Mo, Nb, W, Ta, Zr, Ga, Mn, Ce component, even if Cr, Al content are reduced, it can also keep very
Good high temperature resistance steam oxidation ability, moreover it is possible to avoid alloy hardening and brittle tendency, while with preferable high temperature
Intensity and toughness, generally, are added after certain component in the alloy, although intensity can increase, under corresponding toughness has
Drop, the application can have elevated temperature strength and Toughness concurrently simultaneously by adding Mo, Nb, W, Ta, Zr, Ga, Mn, Ce simultaneously.
Described Mo, Nb, W, Ta, Zr, Ga, Mn, Ce specific addition are related to the concrete composition of FeCrAl based alloys, this
Application can not only hold preferable high temperature resistance by the way that the total weight percent content of Cr, Al alloying element is more than or equal into 17%
Oxidation susceptibility, moreover it is possible to corrosion resistance, by the way that the total weight percent content of Mo, Nb, W, Ta, Zr alloying element is more than
Total weight percent sum equal to 3.1%, Mo and W alloy element is less than or equal to 2.0%, so as to prepare FeCrAl
The Laves second phase particles of a large amount of disperses are separated out during based alloy, Alloy At Room Temperature mechanical property and elevated temperature strength is improved.
Alloy of the present invention by rationally controlling each component between ratio, between alloying element within this range
Interaction, the high temperature oxidation resistance of FeCrAl based alloys can not only be ensured, can avoid Cr, Al content are too high from causing
Alloy hardening and brittle tendency, while having higher elevated temperature strength and Toughness concurrently.It can be used as in power producer
The material of the core structure body such as can, screen work.
Further, the ratio of Cr, AI alloying element content summation and Mo, Nb, W, Ta, Zr alloying element content summation
It is worth for 2.6-6.7.
Further there is provided a kind of nuclear reactor Cr, AI alloying element described in FeCrAl base alloy materials
Total weight percent and for 17.0-20.0%, the total weight percent of Mo, W, Nb, Ta, Zr alloying element and be：3.1—
6.45%.
The technical program further optimizes to high temperature oxidation resistance, the corrosion resistance of FeCrAl based alloys, the function
It is related directly to Cr, Al content, by the total weight percent of Cr, AI alloying element and when being set to 17.0-20.0%, close
High temperature oxidation resistance, the corrosion resistance of gold are optimal；The gross weight of Mo, W, Nb, Ta, Zr alloying element in FeCrAl based alloys
Percentage and it is：When 3.1-6.45%, whole alloy has more excellent room-temperature mechanical property, elevated temperature strength
Further, a kind of nuclear reactor is less than or equal to FeCrAl base alloy material C element total weight percents
0.008%, the total weight percent that N element total weight percent is less than or equal to 0.005%, O alloying elements is less than or equal to
0.003%.
Further, a kind of nuclear reactor FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：12.5~14.5%, Al：3.5~5.5%, Mo：1.5~3.0%, Nb：1.0~3.0%, W：0~0.2%,
Ta：0.1~0.15%, Zr：0.05~0.10%, Ga：0.1~0.2%, Mn：0.1~0.2%, Ce：0.05~0.1%, C：
≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
Further, a kind of nuclear reactor FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：12.7%, Al：4.5%, Mo：1.9%, W：0.1%, Nb：1.0%, Ta：0.1%, Zr：0.10%, Ga：
0.1%, Mn：0.1%, Ce：0.05%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
Further, a kind of nuclear reactor FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：14.5%, Al：5.5%, Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%, Zr：0.05%, Ga：
0.1~0.2%, Mn：0.1~0.2%, Ce：0.05~0.1%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%,
Surplus is Fe and impurity.
Further, a kind of nuclear reactor FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：13.1%, Al：3.9%, Mo：1.7%, W：0.1%, Nb：2.5%, Ta：0.12%, Zr：0.08%, Ga：
0.2%th, Mn：0.1%th, Ce：0.05%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
Further, a kind of nuclear reactor FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：12.9%, Al：4.5%, Mo：1.9%, W：0.1%, Nb：2.0%, Ta：0.1%, Zr：0.1%, Ga：
0.2%th, Mn：0.15%th, Ce：0.08%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
The present invention also provides a kind of preparation method of FeCrAl base alloy materials, including following operating procedure,
(1) FeCrAl based alloys are mixed in proportion, melting prepares ingot casting；
(2) ingot casting homo genizing annelaing at 1150 DEG C~1200 DEG C, and it is incubated 4-5h；
(3) oxide skin on ingot casting surface after homogenizing annealing, high temperature forging are removed, initial forging temperature is：1080 DEG C~1100
DEG C, final forging temperature is：More than or equal to 850 DEG C, forging ratio is more than 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
Speed is：780~800 DEG C of processing 0.5-1.5h, hot rolled plate after heat treatment, hot-rolled temperature is less than or equal to 780 DEG C, material deformation
Amount is more than or equal to 60%；
(5) by the sheet material Ageing Treatment after hot rolling, aging temp is：780 DEG C~800 DEG C, aging time is：20h~
26h；
(6) it is the hot rolled plate after Ageing Treatment is cold rolling, intermediate anneal temperature and final annealing temperature in cold-rolled process
Less than or equal to 715 DEG C, cold rolling material deflection is more than or equal to 40%, produces.
In preparation method of the present invention：Following two conditions are met, one is that alloy hot-rolled temperature is less than or equal to 780 DEG C,
Deflection be more than or equal to 60%, and hot rolling after material need at 780~800 DEG C heat aging handle 20-26h after can be cold rolling；Two
It is that the hot rolled plate progress after heat aging is handled is cold rolling, and the intermediate anneal temperature and final annealing temperature in cold-rolled process are small
In equal to 715 DEG C, cold rolling reduction is less than or equal to 40%.
The technical program adds the FeCrAl of Mo, Nb, W, Ta, Zr alloying element to controlling Cr, AI alloying element content
Based alloy, carries out the working processes such as zerolling, long-time timeliness, heat treatment, makes the FeCrAl based alloys prepared：1) exist
Under 1000 DEG C of water vapor conditions have excellent high temperature oxidation resistance, 2) under 800 DEG C of high temperature alloy have elevated temperature strength and
Structure stability, at room temperature with very high mechanical strength and the plasticity properly processed.
The interaction between alloying element in FeCrAl based alloys of the present invention, with reference to zerolling, long-time
The processing technology such as timeliness and heat treatment, generates extraordinary effect：Alloy of the present invention is through zerolling, long-time timeliness and warm
The phases of Laves second of small and dispersed distribution are obtained after handling process processing, significantly improving the mechanical property of alloy, (room temperature is strong
Toughness and elevated temperature strength) and alloy structure heat endurance.
The present invention compared with prior art, has the following advantages and advantages：
(1) FeCrAl based alloys of the present invention, the total weight percent of Cr, AI alloying element be more than or equal to
17%, and the total weight percent of Cr alloying elements is more than or equal to 12.7%, FeCrAl base alloy materials is possessed preferable height
Warm oxidation susceptibility and corrosion resistance；Wherein, the total weight percent content of Mo, Nb, W, Ta, Zr alloying element is more than or equal to
The total weight percent sum of 3.1%, Mo and W alloy element is that the Laves the of a large amount of disperses can be separated out less than or equal to 2.0%
Secondary phase particle, improves Alloy At Room Temperature mechanical property and elevated temperature strength.And in FeCrAl based alloys alloying element interphase interaction,
Enable alloy material that there is excellent high-temperature steam oxidation resistance, irradiation behaviour, alloy material has under 8000 DEG C of high temperature
Higher elevated temperature strength and thermal structure stability, and there is higher mechanical strength and the plasticity properly processed at room temperature.
(2) present invention uses Low Temperature Hot Rolling, long-time timeliness, heat treatment in the method for preparing FeCrAl base alloy materials
Etc. technique,.Make alloy material that there is very excellent high temperature oxidation resistance, pyrogenic steam oxidation speed under 1000 DEG C of vapor
Rate uses preparation technology of the present invention well below current commercial nuclear power cladding materials Zr-4, obtains small and dispersed distribution
The phases of Laves second, significantly improve the mechanical property of alloy and the structure stability of alloy structure.
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 1：
A kind of nuclear reactor FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：12.7%, Al：4.5%, Mo：1.9%, W：0.1%, Nb：1.0%, Ta：0.1%, Zr：0.10%, Ga：
0.1%, Mn：0.1%, Ce：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, wherein miscellaneous
Matter meets the requirement of commercial industrial pure iron, the total weight percent of Cr, AI alloying element and be 17.2%, Mo, Nb, W, Ta, Zr
Total weight percent and for 3.2%, Cr, AI alloying element content summation and Mo, Nb, Ta alloying element content summation
Ratio is 5.4.
Embodiment 2：
A kind of nuclear reactor FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：14.5%, Al：5.5%, Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%, Zr：0.05%, Ga：
0.2%th, Mn：0.1%th, Ce：0.01%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, wherein miscellaneous
Matter meets the requirement of commercial industrial pure iron, the total weight percent of Cr, AI alloying element and be 20%, Mo, Nb, W, Ta, Zr's
Total weight percent and for 3.9%, Cr, AI alloying element content summation and Mo, Nb, W, Ta, Zr alloying element content are total
The ratio of sum is 5.1.
Embodiment 3：
A kind of nuclear reactor FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：13.1%, Al：3.9%, Mo：1.7%, W：0.1%, Nb：2.5%, Ta：0.12%, Zr：0.08%, Ga：
0.2%th, Mn：0.1%th, Ce：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, wherein miscellaneous
Matter meets the requirement of commercial industrial pure iron, the total weight percent of Cr, AI alloying element and be 17%, and Mo, Nb, W, Ta, Zr are closed
The total weight percent of gold element and for 4.5%, Cr, AI alloying element content summation is first with Mo, Nb, W, Ta, Zr alloy
The ratio of cellulose content summation is 3.8.
Embodiment 4：
A kind of nuclear reactor FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：12.9%, Al：4.5%, Mo：1.9%, W：0.1%, Nb：2.0%, Ta：0.1%, Zr：0.1%, Ga：
0.2%th, Mn：0.15%th, Ce：0.08%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, wherein miscellaneous
Matter meets the requirement of commercial industrial pure iron, the total weight percent of Cr, AI alloying element and be 17.4%, Mo, Nb, W, Ta, Zr
The total weight percent of alloying element and for 5.2%, Cr, AI alloying element content summation and Mo, Nb, W, Ta, Zr alloy
The ratio of constituent content summation is 3.3.
Embodiment 5：
A kind of nuclear reactor FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：13.5%, Al：4.5%, Mo：1.6%, W：0.2%, Nb：1.5%, Ta：0.1%, Zr：0.15%, Ga：
0.1%th, Mn：0.1%th, Ce：0.01%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, wherein miscellaneous
Matter meets the requirement of commercial industrial pure iron, the total weight percent of Cr, AI alloying element and be 18%, Mo, Nb, W, Ta, Zr's
Total weight percent and for 3.55%, Cr, AI alloying element content summation and Mo, Nb, W, Ta, Zr alloying element content are total
The ratio of sum is 5.1.
A kind of nuclear reactor of embodiment 1-5 is prepared with FeCrAl base alloy materials using following methods, is had
Preparation comprises the following steps：
(1) alloying element and ratio of the high purity alloys with ingot iron and purity more than 99.9% as described in embodiment 1-5
Example dispensing, 20-30 kilograms of ingot castings are prepared with vacuum induction melting furnace；
(2) ingot casting homo genizing annelaing at 1150 DEG C~1200 DEG C, and it is incubated 4-5h；
(3) oxide skin on ingot casting surface after homogenizing annealing, high temperature forging are removed, initial forging temperature is：1080 DEG C~1100
DEG C, final forging temperature is：More than or equal to 850 DEG C, forging ratio is more than 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
Speed is：780~800 DEG C of processing 0.5-1.5h, hot rolled plate after heat treatment, hot-rolled temperature is less than or equal to 780 DEG C, material deformation
Amount is more than or equal to 60%；
(5) by the sheet material Ageing Treatment after hot rolling, aging temp is：780 DEG C~800 DEG C, aging time is：20h~
26h；
(6) it is the hot rolled plate after Ageing Treatment is cold rolling, intermediate anneal temperature and final annealing temperature in cold-rolled process
Less than or equal to 715 DEG C, cold rolling material deflection is more than or equal to 40%, produces.
Comparative example 1#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：14.5%, Al：5.5%, C：0.008%, N：0.005%, O：0.003%, surplus be Fe and impurity, wherein
Impurity meets the requirement of commercial industrial pure iron.
Comparative example 1# and the difference of embodiment 1 are：It is not added with Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%,
Zr：0.05%, Ga：0.1%th, Mn：0.1%th, Ce：0.01%.
Comparative example 2#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：14.5%, Al：5.5%, Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%, Zr：0.05%, C：
0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, and wherein impurity meets the requirement of commercial industrial pure iron.
Comparative example 2# and the difference of embodiment 1 are：It is not added with Ga：0.1%th, Mn：0.1%th, Ce：0.01%.
Comparative example 3#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：14.5%, Al：5.5%, Ga：0.1%th, Mn：0.1%th, Ce：0.01%, C：0.008%, N：0.005%, O：
0.003%, surplus is Fe and impurity, and wherein impurity meets the requirement of commercial industrial pure iron.
Comparative example 3# and the difference of embodiment 1 are：It is not added with Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%,
Zr：0.05%.
Comparative example 4#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：18%, Al：8%, Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%, Zr：0.05%, Ga：
0.1%th, Mn：0.1%th, Ce：0.01%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, wherein miscellaneous
Matter meets the requirement of commercial industrial pure iron.
Comparative example 4# and the difference of embodiment 1 are：Cr：18%, Al：8%, i.e. Cr, Al content are higher than embodiment 1.
Comparative example 5#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：8%, Al：2%, Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%, Zr：0.05%, Ga：0.1~
0.2%th, Mn：0.1%th, Ce：0.01%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, wherein miscellaneous
Matter meets the requirement of commercial industrial pure iron.
Comparative example 5# and the difference of embodiment 1 are：Cr：8%, Al：2%, i.e. Cr, Al content are less than embodiment 1.
Described in a kind of nuclear reactor FeCrAl base alloy materials, comparative example 1# -5# described in embodiment 1-5
Alloying element and its ratio difference of commercial FeCrAl base alloy materials are as shown in table 1 below：
Note：The ratio of alloying element described in table 1 is calculated using percentage by weight %.
FeCrAl base alloy materials of the present invention described in embodiment 1-5 and the commercial FeCrAl bases described in comparative example 1# -5#
The Performance Analysis of alloy material is as follows, as shown in table 2：
Analysis result：
From the experimental data of table 2：
Embodiment 1 to embodiment 5 is respectively provided with good high temperature oxidation resistance and heat endurance, while having preferable height concurrently
Warm intensity and Toughness.
Contrasted from embodiment 1 to embodiment 5 and comparative example 1#-3#：Embodiment 1# -3# be added without Mo, Nb, W, Ta,
Zr, Ga, Mn, Ce element, reduce merely Cr, Al content, not only high temperature oxidation resistance reduction, and elevated temperature strength and room temperature
Toughness is also reduced.
Contrasted from embodiment 1 to embodiment 5 and comparative example 4#：When the content of trace element is constant, increase Cr, Al
Content, toughness can be caused to reduce.
Contrasted from embodiment 1 to embodiment 5 and comparative example 5#：When the content of trace element is constant, Cr, Al are reduced
Content, high temperature oxidation resistance can be caused to reduce.
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 (10)
1. a kind of nuclear reactor FeCrAl base alloy materials, it is characterised in that weight percentage, by with the following group
It is grouped into, Cr, AI, Mo, Nb, W, Ta, Zr, Ga, Mn, Ce, C, N, O, Fe, impurity, wherein, the gross weight of Cr, AI alloying element
Percentage be more than or equal to 17%, and Cr alloying elements total weight percent be more than or equal to 12.7%, Mo, Nb, W, Ta, Zr close
The total weight percent sum that the total weight percent content of gold element is more than or equal to 3.1%, Mo and W alloy element be less than etc.
In 2.0%.
2. a kind of nuclear reactor FeCrAl base alloy materials according to claim 1, it is characterised in that：It is described
The ratio of Cr, AI alloying element content summation and Mo, Nb, W, Ta, Zr alloying element content summation is 2.6-6.7.
3. a kind of nuclear reactor FeCrAl base alloy materials according to claim 1 or 2, it is characterised in that：Institute
State the total weight percent of Cr, AI alloying element and for 17.0-20.0%, the gross weight hundred of Mo, W, Nb, Ta, Zr alloying element
Divide ratio and be：3.1-6.45%.
4. a kind of nuclear reactor FeCrAl base alloy materials according to claim 1, it is characterised in that：C element
Total weight percent is less than or equal to 0.008%, and N element total weight percent is less than or equal to the gross weight of 0.005%, O alloying elements
Measure percentage and be less than or equal to 0.003%.
5. a kind of nuclear reactor FeCrAl base alloy materials according to claim 3, it is characterised in that：By weight
Percentage composition meter, it is composed of the following components,
Cr：12.7~14.5%, Al：3.5~5.5%, Mo：1.5~3.0%, Nb：1.0~3.0%, W：0~0.2%, Ta：
0.1~0.15%, Zr：0.05~0.10%, Ga：0.1~0.2%, Mn：0.1~0.2%, Ce：0.05~0.1%, C：≤
0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
6. a kind of nuclear reactor FeCrAl base alloy materials according to claim 5, it is characterised in that：By weight
Percentage composition meter, it is composed of the following components,
Cr：12.7%, Al：4.5%, Mo：1.9%, W：0.1%, Nb：1.0%, Ta：0.1%, Zr：0.10%, Ga：0.1%,
Mn：0.1%, Ce：0.05%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
7. a kind of nuclear reactor FeCrAl base alloy materials according to claim 5, it is characterised in that：By weight
Percentage composition meter, it is composed of the following components,
Cr：14.5%, Al：5.5%, Mo：1.5%, W：0.2%, Nb：2.0%, Ta：0.15%, Zr：0.05%, Ga：0.1~
0.2%th, Mn：0.1~0.2%, Ce：0.05~0.1%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is
Fe and impurity.
8. a kind of nuclear reactor FeCrAl base alloy materials according to claim 5, it is characterised in that：By weight
Percentage composition meter, it is composed of the following components,
Cr：13.1%, Al：3.9%, Mo：1.7%, W：0.1%, Nb：2.5%, Ta：0.12%, Zr：0.08%, Ga：
0.2%th, Mn：0.1%th, Ce：0.05%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
9. a kind of nuclear reactor FeCrAl base alloy materials according to claim 5, it is characterised in that：By weight
Percentage composition meter, it is composed of the following components,
Cr：12.9%, Al：4.5%, Mo：1.9%, W：0.1%, Nb：2.0%, Ta：0.1%, Zr：0.1%, Ga：0.2%th,
Mn：0.15%th, Ce：0.08%, C：≤ 0.008%, N：≤ 0.005%, O：≤ 0.003%, surplus is Fe and impurity.
10. a kind of preparation of nuclear reactor FeCrAl base alloy materials according to claim 1 to 9 any one
Method, it is characterised in that：Including following operating procedure：
(1) FeCrAl based alloys are mixed in proportion, melting prepares ingot casting；
(2) ingot casting homo genizing annelaing at 1150 DEG C~1200 DEG C, and it is incubated 4-5h；
(3) oxide skin on ingot casting surface after homogenizing annealing, high temperature forging are removed, initial forging temperature is：1080 DEG C~1100 DEG C, eventually
Forging temperature is：More than or equal to 850 DEG C, forging ratio is more than 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 speed
For：780~800 DEG C/0.5-1.5h, hot rolled plate after heat treatment, hot-rolled temperature is less than or equal to 780 DEG C, and material deflection is more than
Equal to 60%；
(5) by the sheet material Ageing Treatment after hot rolling, aging temp is：780 DEG C~800 DEG C, aging time is：20h~26h；
(6) hot rolled plate after Ageing Treatment is cold rolling, intermediate anneal temperature and final annealing temperature in cold-rolled process are less than
Equal to 715 DEG C, cold rolling material deflection is more than or equal to 40%, produces.
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN110918649A (en) * | 2019-10-16 | 2020-03-27 | 宁夏北鼎新材料产业技术有限公司 | FeCrAl alloy tube material for light water reactor cladding and rolling method 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 |
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| CN106399846A (en) * | 2016-10-12 | 2017-02-15 | 苏州热工研究院有限公司 | FeCrAl alloy material for preparing Nuclear reactor fuel cladding material |
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Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN110918649A (en) * | 2019-10-16 | 2020-03-27 | 宁夏北鼎新材料产业技术有限公司 | FeCrAl alloy tube material for light water reactor cladding and rolling method 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 |
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