CN107217205A - A kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials and preparation method thereof - Google Patents
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials and preparation method thereof Download PDFInfo
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Abstract
The invention discloses a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, it is composed of the following components, Cr, AI, Mo, Nb, Si, Ti, V, Mn, Ni, La, C, N, O, Fe, impurity, wherein, Cr, AI, the total weight percent of Si alloying elements and more than or equal to 17%, Mo, Nb, Ti, the total weight percent of V alloy element and more than or equal to 3.0%, FeCrAl based alloys of the present invention, Alloy At Room Temperature mechanical property and elevated temperature strength can be effectively improved, and in FeCrAl based alloys alloying element interphase interaction, enable alloy material that there is excellent high-temperature steam oxidation resistance, irradiation behaviour, there is very excellent high temperature oxidation resistance under 1000 DEG C of water vapor conditions.
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
Can 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, and produce that reactor hydrogen is quick-fried is leaked with a large amount of radioactive products
Etc. nuclear catastrophe consequence.So, of future generation and following advanced nuclear power presurized water reactor is with can material with now being closed with nuclear power zirconium
Golden cladding materials is compared, it is necessary to possess more preferable high temperature resistance steam oxidation ability, elevated temperature strength and high-temperature stability, can be one
Fix time and interior bigger safe clearance is provided and avoids potential serious reactor core from melting accident, also referred to as crash-proof cladding materials.
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 in commercial FeCrAl base alloy materials because contain compared with
High 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 brings great potential safety hazard.Moreover, higher Cr, Al content FeCrAl based alloys room temperature mechanics plasticity compared with
Difference, causes sheet alloy and thin-wall pipes processing difficulties.
Based on this, study and develop a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials of design and its system
Preparation Method.
The content of the invention
It is an object of the invention to：A kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials are provided, in base
Mo, Nb, Ti and V alloy element of special ratios are added in body, and reduces the content of Cr, Al alloying element, i.e., to FeCrAl bases
Alloying component is adjusted improvement, solves existing commercial FeCrAl base alloy materials in reactor operation operating mode thermal failure and spoke
Hardening and embrittlement are serious according under the conditions of, the technical problem such as room temperature mechanics plasticity is poor.
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 FeCrAl base alloy materials have higher elevated temperature strength and structure stability, in room
Temperature is lower 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 fuel element involucrum FeCrAl base alloy materials, weight percentage, by with the following group
Be grouped into, Cr, AI, Mo, Nb, Si, Ti, V, Mn, Ni, La, C, N, O, Fe, impurity, wherein, Cr, AI, Si alloying element it is total
Percentage by weight and more than or equal to 17%, Mo, Nb, Ti, the total weight percent of V alloy element and more than or equal to 3.0%.
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, Ti, V, SI alloying element, while to Cr, Al content is controlled, reduce Cr, Al content, to keep away
Exempt from 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, Si, Ti, V, Mn, Ni, La 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, Si, Ti, V, Mn, Ni, La simultaneously.
Described Mo, Nb, Si, Ti, V, Mn, Ni, La specific addition are related to the concrete composition of FeCrAl based alloys, this
Application can not only hold preferably anti-by the way that the total weight percent content of Cr, Al and Si alloying element is more than or equal into 17%
High temperature oxidation resistance, moreover it is possible to corrosion resistance, by by Mo, Nb, Ti, V alloy element total weight percent content >=
3.0%, so as to separate out the Laves second phase particles of a large amount of disperses when preparing FeCrAl based alloys, improve Alloy At Room Temperature
Mechanical property and elevated temperature strength.
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, Cr, AI, Si alloying element content summation and Mo, Nb, Ti, the ratio of V alloy constituent content summation
It is worth for 2.6-6.8.
Further there is provided Cr, AI alloying element in a kind of FeCrAl based alloys, Mo, Nb, Ta alloying element it is preferred,
The total weight percent of Cr, AI, Si alloying element and for 17.0-20.4%, Mo, Nb, Ti, the gross weight of V alloy element
Percentage and it is：3.0-6.7%.
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 and Si content, the total weight percent of Cr, AI, Si alloying element and 17.0 will be set to-
When 20.4%, high temperature oxidation resistance, the corrosion resistance of alloy are optimal；Mo, Nb, Ti, V alloy element in FeCrAl based alloys
Total weight percent and be：When 3.0-6.7%, whole alloy has more excellent room-temperature mechanical property, elevated temperature strength.
Further, preferred, the gross weight hundred of Cr alloying elements is carried out to the alloying element content in FeCrAl based alloys
Divide than being less than or equal to 12.7%, the total weight percent of C alloy element is less than or equal to the gross weight hundred of 0.008%, N alloying elements
Divide and be less than or equal to 0.003% than the total weight percent less than or equal to 0.003%, O alloying elements.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with
The following group is grouped into,
Cr：12.5~14.5%, Al：3.5~5.5%, Mo：1.5~3%, Nb：1~3%, Si：0.1~0.4%, Ti：
0.1~0.5%, V：0.1~0.2%, Mn+Ni：0.1~0.2%, La：0.05~0.1%, C：≤ 0.008%, N：≤
0.005%, O：≤ 0.003%, surplus is Fe and impurity.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with
The following group is grouped into,
Cr：12.5%, Al：4.1%, Mo：1.5%, Nb：1.3%, Si：0.4%, Ti：0.1%, V：0.1%, Mn+Ni：
0.1%, La：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with
The following group is grouped into,
Cr：14.5%, Al：3.5%, Mo：3%, Nb：3%, Si：0.4%, Ti：0.5%, V：0.2%, Mn+Ni：
0.2%, La：0.1%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with
The following group is grouped into,
Cr：13.5%, Al：4.9%, Mo：1.5%, Nb：1%, Si：0.3%, Ti：0.3%, V：0.2%, Mn+Ni：
0.2%, La：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with
The following group is grouped into,
Cr：12.9%, Al：3.9%, Mo：2.9%, Nb：2.4%, Si：0.3%, Ti：0.3%, V：0.2%, Mn+Ni：
0.2%, La：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) high purity alloys for being more than 99.9% with ingot iron and purity are mixed according to FeCrAl base alloy materials ratio,
Ingot casting is prepared into vacuum induction furnace suede material；
(2) ingot casting for obtaining step (1) carries out high temperature homogenizing annealing, and ingot casting is uniformly degenerated at 1150 DEG C~13 DEG C
Temperature, and it is incubated 3-10h；
(3) oxide skin on ingot casting surface after homogenizing annealing, high temperature forging are removed, initial forging temperature is：1050 DEG C~1150
DEG C, final forging temperature is：More than or equal to 800 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
Temperature is：Hot rolled plate after 0.5-1.5h, heat treatment is handled at 780~800 DEG C, hot-rolled temperature is less than or equal to 810 DEG C, and material becomes
Shape amount is more than or equal to 65%；
(5) sheet material after hot rolling is subjected to heat aging processing, aging temp is：750 DEG C~800 DEG C, aging time is：
20h~100h；
(6) hot rolled plate after heat aging is handled is cold rolling, intermediate anneal temperature and final annealing temperature in cold-rolled process
Degree is less than or equal to 715 DEG C, and cold rolling reduction is more than or equal to 35%, 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 810 DEG C,
Deflection be more than or equal to 65%, and hot rolling after material need at 750~800 DEG C heat aging processing 20-100 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 35%.
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) the FeCrAl base alloy materials of the present invention for nuclear-power reactor can, Cr：12.5~
14.5%, Al：3.5~5.5%, Mo：1.5~3%, Si：0.1~0.4%, Nb：1~3%, Ti：0.1~0.5%, V：0.1
~0.2%, the total weight percent of Cr, AI, Si alloying element and more than or equal to 17%, with preferable high temperature oxidation resistance
And corrosion resistance；The total weight percent content of Mo, Nb, Ti and V alloy element is more than or equal to 3.0%, can separate out largely more
Scattered Laves second phase particles, improve Alloy At Room Temperature mechanical property and elevated temperature strength.And alloying element in FeCrAl based alloys
Interphase interaction, enable alloy material that there is excellent high-temperature steam oxidation resistance, irradiation behaviour, at room temperature with compared with
High mechanical strength and the plasticity properly processed.
(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 thermal 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 fuel element involucrum FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：12.5%, Al：4.1%, Mo：1.5%, Nb：1.3%, Si：0.4%, Ti：0.1%, V：0.1%, Mn+Ni：
0.1%, La：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, and wherein impurity content meets
The standard of current commercial industrial pure iron and ferritic stainless steel, the total weight percent of Cr, AI, si alloying element and be 17%,
Mo, Nb, Ti, the total weight percent of V alloy element and for 3.0%, Cr, AI, si alloying element content summation and Mo,
Nb, Ti, the ratio of V alloy constituent content summation are 2.9.
Embodiment 2：
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：14.5%, Al：3.5%, Mo：3%, Nb：3%, Si：0.4%, Ti：0.5%, V：0.2%, Mn+Ni：
0.2%, La：0.1%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, and wherein impurity content meets
The standard of current commercial industrial pure iron and ferritic stainless steel, the total weight percent of Cr, AI, si alloying element and be
18.4%, Mo, Nb, Ti, the total weight percent of V alloy element and for 6.7%, Cr, AI, si alloying element content is total
With with the ratio of Mo, Nb, Ti, V alloy constituent content summation be 2.7.
Embodiment 3：
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：13.5%, Al：4.9%, Mo：1.5%, Nb：1%, Si：0.3%, Ti：0.3%, V：0.2%, Mn+Ni：
0.2%, La：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, and wherein impurity meets commercial
The requirement of ingot iron, the total weight percent of Cr, AI, si alloying element and be 18.7%, Mo, Nb, Ti, V alloy element
Total weight percent and for 3.0%, Cr, AI, si alloying element content summation and Mo, Nb, Ti, V alloy constituent content are total
The ratio of sum is 6.1.
Embodiment 4：
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：12.9%, Al：3.9%, Mo：2.9%, Nb：2.4%, Si：0.3%, Ti：0.3%, V：0.2%, Mn+Ni：
0.2%, La：0.08%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, Cr, AI, si alloying element
Total weight percent and be 18.7%, Mo, Nb, Ti, the total weight percent of V alloy element and be 3.0%, the Cr, AI,
The ratio of si alloying element contents summation and Mo, Nb, Ti, V alloy constituent content summation is 6.1.
Embodiment 5：
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials, weight percentage, by with the following group
It is grouped into,
Cr：12.7%, Al：4.5%, Mo：2.9%, Nb：2.0%, Si：0.4%, Ti：0.3%, V：0.2%, Mn+Ni：
0.2%, La：0.07%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity, Cr, AI, si alloying element
Total weight percent and be 17.5%, Mo, Nb, Ti, the total weight percent of V alloy element and be 5.4%, the Cr, AI,
The ratio of si alloying element contents summation and Mo, Nb, Ti, V alloy constituent content summation is 3.2.
Embodiment 1-5 is prepared using following methods, and specific preparation method 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 for obtaining step (1) carries out high temperature homogenizing annealing, and annealing temperature is：1150 DEG C~1300 DEG C, protect
3~10h of temperature；
(3) oxide skin on ingot casting surface after homogenizing annealing, high temperature forging are removed, initial forging temperature is：1050 DEG C~1150
DEG C, final forging temperature is：More than or equal to 800 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
Temperature is：780~800 DEG C/0.5-1.5h, hot rolled plate after heat treatment, hot-rolled temperature is less than or equal to 810 DEG C, material deflection
More than or equal to 65%；
(5) sheet material after hot rolling is subjected to heat aging processing, aging temp is：750 DEG C~800 DEG C, aging time is：
20h~100h；
(6) hot rolled plate after heat aging is handled is cold rolling, intermediate anneal temperature and final annealing temperature in cold-rolled process
Degree is less than or equal to 710 DEG C, and cold rolling reduction is more than or equal to 35%, produces.
Comparative example 1#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：14.5%, Al：3.5%, 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 2 are：Without Mo：3%, Nb：3%, Si：0.4%, Ti：0.5%, V：
0.2%, Mn+Ni：0.2%, La：0.1%.
Comparative example 2#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：14.5%, Al：3.5%, Mo：3%, Nb：3%, C：0.008%, N：0.005%, O：0.003%, surplus is
Fe and impurity, wherein impurity meet the requirement of commercial industrial pure iron.
Comparative example 2# and the difference of embodiment 2 are：Without Si：0.4%, Ti：0.5%, V：0.2%, Mn+Ni：
0.2%, La：0.1%.
Comparative example 3#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：14.5%, Al：3.5%, Si：0.4%, Ti：0.5%, V：0.2%, Mn+Ni：0.2%, La：0.1%, 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 comparative example 2 are：Without Mo：3%, Nb：3%.
Comparative example 4#:
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：18%, Al：8%, Mo：3%, Nb：3%, Si：0.4%, Ti：0.5%, V：0.2%, Mn+Ni：0.2%,
La：0.1%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
Comparative example 4# and the difference of embodiment 2 be, Cr:18%, AI:8%, i.e. Cr, AI content are higher than embodiment 2.
Comparative example 5#：
Commercial FeCrAl base alloy materials, weight percentage is composed of the following components,
Cr：8%, Al：2.5%, Mo：3%, Nb：3%, Si：0.4%, Ti：0.5%, V：0.2%, Mn+Ni：0.2%,
La：0.1%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
Comparative example 5# and the difference of embodiment 2 be, Cr:8%, AI:2.5%, i.e. Cr, AI content are less than embodiment 2.
Its ratio of embodiment 1-5 and comparative example 1#-5# alloying element such as table 1 below；
Note：Wherein, the ratio of the alloying element described in table 1 is with weight %；Each implement in table 1
The equal surplus of example, comparative example is Fe and impurity, and impurity meets the requirement of commercial industrial pure iron.
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 shown in table 2 below：
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#：Simple reduction Cr, Al content, not only anti-height
Warm oxidation susceptibility reduction, and elevated temperature strength reduction.
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 fuel element involucrum FeCrAl base alloy materials, it is characterised in that weight percentage,
It is composed of the following components, Cr, AI, Mo, Nb, Si, Ti, V, Mn, Ni, La, C, N, O, Fe, impurity, wherein, Cr, AI, Si alloy member
The total weight percent of element and more than or equal to 17%, Mo, Nb, Ti, the total weight percent of V alloy element and it is more than or equal to
3.0%.
2. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 1, its feature exists
In：The ratio of Cr, AI, Si alloying element content summation and Mo, Nb, V, Ti alloying element content summation is 2.6-6.8.
3. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 1 or 2, its feature
It is：The total weight percent of Cr, AI, Si alloying element and be 17.0-20.4%, Mo, Nb, Ti, V alloy element
Total weight percent and it is：3.0-6.7%.
4. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 1, its feature exists
In：The total weight percent of Cr alloying elements is less than or equal to 12.7%, and the total weight percent of C alloy element is less than or equal to
The total weight percent of 0.008%, N alloying element be less than or equal to 0.003%, O alloying elements total weight percent be less than etc.
In 0.003%.
5. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 3, its feature exists
In：Weight percentage, it is composed of the following components,
Cr：12.5~14.5%, Al：3.5~5.5%, Mo：1.5~3%, Nb：1~3%, Si：0.1~0.4%, Ti：0.1
~0.5%, V：0.1~0.2%, Mn+Ni：0.1~0.2%, La：0.05~0.1%, C：≤ 0.008%, N：≤ 0.005%,
O：≤ 0.003%, surplus is Fe and impurity.
6. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 5, its feature exists
In：Weight percentage, it is composed of the following components,
Cr：12.5%, Al：4.1%, Mo：1.5%, Nb：1.3%, Si：0.4%, Ti：0.1%, V：0.1%, Mn+Ni：
0.1%, La：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
7. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 5, its feature exists
In：Weight percentage, it is composed of the following components,
Cr：14.5%, Al：3.5%, Mo：3%, Nb：3%, Si：0.4%, Ti：0.5%, V：0.2%, Mn+Ni：0.2%,
La：0.1%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
8. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 5, its feature exists
In：Weight percentage, it is composed of the following components,
Cr：13.5%, Al：4.9%, Mo：1.5%, Nb：1%, Si：0.3%, Ti：0.3%, V：0.2%, Mn+Ni：0.2%,
La：0.05%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
9. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy materials according to claim 5, its feature exists
In：Weight percentage, it is composed of the following components,
Cr：12.9%, Al：3.9%, Mo：2.9%, Nb：2.4%, Si：0.3%, Ti：0.3%, V：0.2%, Mn+Ni：
0.2%, La：0.08%, C：0.008%, N：0.005%, O：0.003%, surplus is Fe and impurity.
10. a kind of nuclear reactor fuel element involucrum FeCrAl based alloy materials according to claim 1 to 9 any one
The preparation method of material, it is characterised in that：Including following operating procedure：
(1) FeCrAl based alloys are mixed in proportion, melting obtains ingot casting；
(2) ingot casting homo genizing annelaing at 1150 DEG C~1300 DEG C, and it is incubated 3-10h；
(3) oxide skin on ingot casting surface after homogenizing annealing, high temperature forging are removed, initial forging temperature is：1050 DEG C~1150 DEG C, eventually
Forging temperature is：More than or equal to 800 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, heat treatment temperature
For：Hot rolled plate after 0.5-1.5h, heat treatment is handled at 780~800 DEG C, hot-rolled temperature is less than or equal to 810 DEG C, material deflection
More than or equal to 65%；
(5) sheet material after hot rolling is subjected to heat aging processing, aging temp is：750 DEG C~800 DEG C, aging time is：20h~
100h；
(6) hot rolled plate 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 710 DEG C, cold rolling reduction is more than or equal to 35%, produces.
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| Title |
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| JUN LIM等: "Design of alumina forming FeCrAl steels for lead or lead-bismuth", 《JOURNAL OF NUCLEAR MATERIALS》 * |
| Y. YAMAMOTO等,: "Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors", 《JOURNAL OF NUCLEAR MATERIALS》 * |
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