CN107217205B - A kind of nuclear reactor fuel element involucrum FeCrAl base alloy material and preparation method thereof - Google Patents
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy material 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 element and be more than or equal to 17%, Mo, Nb, Ti, the total weight percent of V alloy element and be more than or equal to 3.0%, FeCrAl based alloy of the present invention, Alloy At Room Temperature mechanical property and elevated temperature strength can be effectively improved, and it interacts between alloying element in FeCrAl based alloy, enable alloy material that there is excellent high-temperature steam oxidation resistance, irradiation behaviour, with very excellent resistant to high temperatures under 1000 DEG C of water vapor conditions Oxidation susceptibility.
Description
Technical field
The invention belongs to fe-based alloy structure material and specialty alloy materials technical field, in particular to a kind of nuclear reactors
Fuel element cladding FeCrAl base alloy material and preparation method thereof.
Background technique
Fuel element is the core component of power producer reactor core, and performance is directly related to the peace of nuclear reactor operation
Quan Xingyu 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 are released big
Calorimetric and explosion gas hydrogen cause cladding materials mechanical property to deteriorate, generate reactor hydrogen it is quick-fried with a large amount of radioactive products outside
The nuclear catastrophes consequence such as let out.So next-generation and following advanced nuclear power presurized water reactor fuel element cladding material and current nuclear power
Zirconium alloy cladding material is compared, it is necessary to have better steam oxidation ability, elevated temperature strength and high-temperature stability resistant to high temperatures, energy
It is enough that bigger safe clearance is provided within a certain period of time and potential serious reactor core is avoided to melt accident, also referred to as crash-proof involucrum
Material.
Crash-proof cladding materials require its can be kept in several hours in 800-1000 DEG C or so steam ambients one very
Low oxidation rate, 2 orders of magnitude at least lower than zircaloy, while the cladding materials are under the hot conditions not less than 800 DEG C
With the mechanical strength for meeting short cycle reliability, the peace of reactor core accident can be just improved when being more than design basis accident in this way
Full allowance.Under the promotion of this tight demand background, world nuclear big country has carried out greatly many candidate 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.
At present mostly commercial FeCrAl base alloy material mostly Cr with higher, Al content ((Cr:15~30%,
Al:6~15%), therefore its high temperature oxidation resistance is more significant.But in commercial FeCrAl base alloy material because contain compared with
High Cr, Al content make that it is hardened under reactor operation operating condition thermal effect and radiation parameter and brittle degree is serious, give reactor
Operation brings great security risk.Moreover, higher Cr, Al content FeCrAl based alloy room temperature mechanics plasticity compared with
Difference leads to sheet alloy and thin-wall pipes processing difficulties.
Based on this, studies and develop and design a kind of nuclear reactor fuel element involucrum FeCrAl base alloy material and its system
Preparation Method.
Summary of the invention
It is an object of the invention to: a kind of nuclear reactor fuel element involucrum FeCrAl base alloy material is 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 base
Alloying component is adjusted improvement, solves existing commercialization FeCrAl base alloy material in reactor operation operating condition thermal failure and spoke
The technical problems such as hardening and embrittlement are serious according under the conditions of, and room temperature mechanics plasticity is poor.
Another object of the present invention is to: a kind of preparation method of FeCrAl base alloy material is provided, pairing gold dollar is passed through
The control of cellulose content, processing technology, so that FeCrAl base alloy material elevated temperature strength with higher 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 material, weight percentage, by with the following group
Be grouped as, Cr, AI, Mo, Nb, Si, Ti, V, Mn, Ni, La, C, N, O, Fe, impurity, wherein Cr, AI, Si alloying element it is total
Weight percent and be more than or equal to 17%, Mo, Nb, Ti, V alloy element total weight percent and be more than or equal to 3.0%.
The hardening of FeCrAl based alloy and the aggravation of embrittlement tendency in order to prevent cause alloy in reactor operation and processing system
It is broken during standby, it should guarantee FeCrAl based alloy with simultaneously compared with strict control on highly resistance pyrogenic steam oxidation capability foundation discussion
Reduce Cr, AI content.Meanwhile containing the FeCrAl based alloy of Cr, AI content appropriate as reactor crash-proof fuel can
Materials'use should also have the following performance other than with above-mentioned performance requirement: 1) at room temperature alloy have higher-strength and
Plasticity provides basis for thin-walled involucrum tubular object extruding；2) be: (not less than 800 DEG C), alloy has higher-strength at high temperature；3)
Be: alloy high-temp tissue is more stable, as far as possible improve alloy recrystallization temperature so that alloy 800 DEG C or more with compared with
Strong thermal structure stability simultaneously postpones alloy grain size and grows up, and the crystal grain of only stable tissue and 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 alloy formula of the present invention is the improvement to existing FeCrAl based alloy, on the basis of existing components
On increase Mo, Nb, Ti, V, SI alloying element, while to Cr, the content of Al is controlled, and reduces Cr, the content of Al, to keep away
Exempt from alloy hardening and brittle tendency.
Applicant passes through the test discovery that studies for a long period of time: it is to reduce Cr on the basis of existing alloy, the content of Al, although
It can be avoided alloy hardening and brittle tendency, but the steam oxidation ability resistant to high temperatures of alloy reduces, and elevated temperature strength and toughness
It is bad.After addition Mo, Nb, Si, Ti, V, Mn, Ni, La component, even if the content of Cr, Al reduce, also it is able to maintain very
Good steam oxidation ability resistant to high temperatures, moreover it is possible to alloy hardening and brittle tendency is avoided, and at the same time having preferable high temperature
Intensity and toughness, in general, after certain component is added in the alloy, although intensity can increase, under corresponding toughness has
Drop, the application pass through while Mo, Nb, Si, Ti, V, Mn, Ni, La are added, and can have both elevated temperature strength and Toughness simultaneously.
The specific additional amount of described Mo, Nb, Si, Ti, V, Mn, Ni, La are related to the concrete composition of FeCrAl based alloy, this
Application can not only be held preferable anti-by the way that the total weight percent content of Cr, Al and Si alloying element is more than or equal to 17%
High temperature oxidation resistance, moreover it is possible to have corrosion resistance, by by Mo, Nb, Ti, V alloy element total weight percent content >=
3.0%, so as to which the Laves second phase particles of a large amount of disperses are precipitated when preparing FeCrAl based alloy, improve Alloy At Room Temperature
Mechanical property and elevated temperature strength.
Alloy of the present invention passes through the ratio between each component of rationally controlling, between alloying element within this range
Interaction, can not only ensure the high temperature oxidation resistance of FeCrAl based alloy, can be avoided that Cr, Al content are excessively high to be caused
Alloy hardening and brittle tendency, while having both higher elevated temperature strength and Toughness.It can be used as in power producer
The material of the core structures body such as fuel element cladding, screen work.
Further, Cr, AI, Si alloying element content summation and Mo, Nb, Ti, V alloy constituent content summation ratio
Value is 2.6-6.8.
Further, provide Cr, AI alloying element in a kind of FeCrAl based alloy, 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, V alloy element total weight
Percentage and are as follows: 3.0-6.7%.
The technical program advanced optimizes high temperature oxidation resistance, the corrosion resistance of FeCrAl based alloy, the function
It is directly related to the content of Cr, Al and Si, by the total weight percent of Cr, AI, Si alloying element and it is set as 17.0-
When 20.4%, high temperature oxidation resistance, the corrosion resistance of alloy are optimal；Mo, Nb, Ti, V alloy element in FeCrAl based alloy
Total weight percent and are as follows: when 3.0-6.7%, entire alloy have superior room-temperature mechanical property, elevated temperature strength.
Further, the alloying element content in FeCrAl based alloy is carried out preferably, the total weight hundred of Cr alloying element
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 total weight hundred of 0.008%, N alloying element
The total weight percent than being less than or equal to 0.003%, O alloying element is divided to be less than or equal to 0.003%.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy material, weight percentage, by with
The following group is grouped as,
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 material, weight percentage, by with
The following group is grouped as,
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 are Fe and impurity.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy material, weight percentage, by with
The following group is grouped as,
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 are Fe and impurity.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy material, weight percentage, by with
The following group is grouped as,
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 are Fe and impurity.
Further, nuclear reactor fuel element involucrum FeCrAl base alloy material, weight percentage, by with
The following group is grouped as,
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 are Fe and impurity.
The present invention also provides a kind of preparation method of FeCrAl base alloy material, including following operating procedure,
(1) high purity alloys with ingot iron and purity greater than 99.9% are mixed according to FeCrAl base alloy material 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 keep the temperature 3-10h；
(3) remove homogenizing annealing after ingot casting surface oxide skin, high temperature forging, initial forging temperature are as follows: 1050 DEG C~1150
DEG C, final forging temperature are as follows: be more than or equal to 800 DEG C, forging ratio is greater than 2；
(4) after removal forging plate surface scale, by surface cleaning, treated that plate is heat-treated, heat treatment
Temperature are as follows: 0.5-1.5h, hot rolled plate after heat treatment are 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) plate after hot rolling is subjected to heat aging processing, aging temp are as follows: 750 DEG C~800 DEG C, aging time are as follows:
20h~100h；
(6) intermediate anneal temperature and final annealing temperature by heat aging treated hot rolled plate cold rolling, in cold-rolled process
Degree be less than or equal to 715 DEG C, cold rolling reduction be more than or equal to 35% to get.
In preparation method of the present invention: meet following two condition, first is that alloy hot-rolled temperature is less than or equal to 810 DEG C,
Deflection is more than or equal to 65%, and material need to heat aging can cold rolling after handling 20-100 at 750~800 DEG C after hot rolling；Two
It is heat aging treated hot rolled plate to be subjected to cold rolling, the intermediate anneal temperature and final annealing temperature in cold-rolled process are small
In being equal to 715 DEG C, cold rolling reduction is less than or equal to 35%.
The interaction between alloying element in FeCrAl based alloy of the present invention, in conjunction with zerolling, long-time
The processing technologys such as timeliness and heat treatment, produce extraordinary effect: alloy of the present invention is through zerolling, long-time timeliness and warm
The second phase of Laves of small and dispersed distribution is obtained after treatment process processing, significantly improving the mechanical property of alloy, (room temperature is strong
Toughness and elevated temperature strength) and alloy structure thermal stability.
Compared with prior art, the present invention having the following advantages and benefits:
(1) the FeCrAl base alloy material of the present invention for nuclear-power reactor fuel element cladding, 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 be more than or equal to 17%, have 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 be precipitated largely more
Scattered Laves second phase particles improve Alloy At Room Temperature mechanical property and elevated temperature strength.And alloying element in FeCrAl based alloy
Between interact, enable alloy material have excellent high-temperature steam oxidation resistance, irradiation behaviour, at room temperature have compared with
High mechanical strength and the plasticity properly processed.
(2) present invention is in the method for preparing FeCrAl base alloy material using Low Temperature Hot Rolling, long-time timeliness, heat treatment
Etc. techniques, make alloy material under 1000 DEG C of vapor have very excellent high temperature oxidation resistance, pyrogenic steam oxidation speed
Rate uses preparation process of the present invention well below current commercial nuclear power cladding materials Zr-4, obtains small and dispersed distribution
The second phase of Laves, significantly improve the mechanical property of alloy and the thermal structure stability of alloy structure.
Specific embodiment
To make the objectives, technical solutions, and advantages of the present invention clearer, below with reference to embodiment, the present invention is made
Further to be described in detail, exemplary embodiment of the invention and its explanation for explaining only the invention, are not intended as to this
The restriction of invention.
Embodiment 1:
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy material, weight percentage, by with the following group
It is grouped as,
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 are Fe and impurity, and wherein impurity content meets
The standard of commercial industrial pure iron and ferritic stainless steel at present, the total weight percent of Cr, AI, si alloying element and be 17%,
Mo, Nb, Ti, V alloy element total weight percent and be 3.0%, Cr, AI, si alloying element content summation and Mo,
Nb, Ti, V alloy constituent content summation ratio be 2.9.
Embodiment 2:
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy material, weight percentage, by with the following group
It is grouped as,
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 are Fe and impurity, and wherein impurity content meets
The standard of commercial industrial pure iron and ferritic stainless steel at present the total weight percent of Cr, AI, si alloying element and is
18.4%, Mo, Nb, Ti, V alloy element total weight percent and be 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 material, weight percentage, by with the following group
It is grouped as,
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 are 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 be 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 material, weight percentage, by with the following group
It is grouped as,
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 are Fe and impurity, Cr, AI, si alloying element
Total weight percent and be 18.7%, Mo, the total weight percent of Nb, Ti, V alloy element and be 3.0%, the Cr, AI,
Si alloying element content summation and the ratio of Mo, Nb, Ti, V alloy constituent content summation are 6.1.
Embodiment 5:
A kind of nuclear reactor fuel element involucrum FeCrAl base alloy material, weight percentage, by with the following group
It is grouped as,
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 are Fe and impurity, Cr, AI, si alloying element
Total weight percent and be 17.5%, Mo, the total weight percent of Nb, Ti, V alloy element and be 5.4%, the Cr, AI,
Si alloying element content summation and the ratio of Mo, Nb, Ti, V alloy constituent content summation are 3.2.
Embodiment 1-5 is all made of following methods and is prepared, specific preparation method the following steps are included:
(1) high purity alloys with ingot iron and purity greater than 99.9% are by alloying element and ratio described in embodiment 1-5
Example ingredient, prepares 20-30 kilograms of ingot castings with vacuum induction melting furnace；
(2) ingot casting for obtaining step (1) carries out high temperature homogenizing annealing, annealing temperature are as follows: 1150 DEG C~1300 DEG C, protects
3~10h of temperature；
(3) remove homogenizing annealing after ingot casting surface oxide skin, high temperature forging, initial forging temperature are as follows: 1050 DEG C~1150
DEG C, final forging temperature are as follows: be more than or equal to 800 DEG C, forging ratio is greater than 2；
(4) after removal forging plate surface scale, by surface cleaning, treated that plate is heat-treated, heat treatment
Temperature are as follows: 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) plate after hot rolling is subjected to heat aging processing, aging temp are as follows: 750 DEG C~800 DEG C, aging time are as follows:
20h~100h；
(6) intermediate anneal temperature and final annealing temperature by heat aging treated hot rolled plate cold rolling, in cold-rolled process
Degree be less than or equal to 710 DEG C, cold rolling reduction be more than or equal to 35% to get.
Comparative example 1#:
Commercial FeCrAl base alloy material, 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# the difference from example 2 is that: be free of 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 material, 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 are
Fe and impurity, wherein impurity meets the requirement of commercial industrial pure iron.
Comparative example 2# the difference from example 2 is that: be free of Si:0.4%, Ti:0.5%, V:0.2%, Mn+Ni:
0.2%, La:0.1%.
Comparative example 3#:
Commercial FeCrAl base alloy material, 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 are 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: being free of Mo:3%, Nb:3%.
Comparative example 4#:
Commercial FeCrAl base alloy material, 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 are Fe and impurity.
Comparative example 4# the difference from example 2 is that, Cr:18%, AI:8%, i.e. Cr, AI content be higher than embodiment 2.
Comparative example 5#:
Commercial FeCrAl base alloy material, 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 are Fe and impurity.
Comparative example 5# the difference from example 2 is that, Cr:8%, AI:2.5%, i.e. Cr, AI content be lower than embodiment 2.
Its ratio of the alloying element of embodiment 1-5 and comparative example 1#-5# such as the following table 1；
Note: where the ratio of alloying element described in table 1 is with weight %；Each implementation in table 1
The equal surplus of example, comparative example is Fe and impurity, and impurity meets the requirement of commercial industrial pure iron.
Commercial FeCrAl base described in FeCrAl base alloy material of the present invention and comparative example 1# -5# described in embodiment 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 all has good high temperature oxidation resistance and thermal stability, while having both preferable height
Warm intensity and Toughness.
It is compared from embodiment 1 to embodiment 5 and comparative example 1# -3#: reducing Cr merely, the content of Al, not only anti-height
Warm oxidation susceptibility reduces, and elevated temperature strength reduces.
It is compared from embodiment 1 to embodiment 5 and comparative example 4#: when the content of microelement is constant, increasing Cr, Al
Content, will lead to toughness reduction.
It is compared from embodiment 1 to embodiment 5 and comparative example 5#: when the content of microelement is constant, reducing Cr, Al
Content, will lead to high temperature oxidation resistance reduction.
Above-described specific embodiment has carried out further the purpose of the present invention, technical scheme and beneficial effects
It is described in detail, it should be understood that being not intended to limit the present invention the foregoing is merely a specific embodiment of the invention
Protection scope, all within the spirits and principles of the present invention, any modification, equivalent substitution, improvement and etc. done should all include
Within protection scope of the present invention.
Claims (6)
1. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy material, it is characterised in that: 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 be Fe and impurity,
The preparation method of the FeCrAl base alloy material, including following operating procedure:
(1) FeCrAl based alloy is mixed in proportion, melting obtains ingot casting；
(2) ingot casting homo genizing annelaing at 1150 DEG C~1300 DEG C, and keep the temperature 3-10h；
(3) remove homogenizing annealing after ingot casting surface oxide skin, high temperature forging, initial forging temperature are as follows: 1050 DEG C~1150 DEG C, eventually
Forge temperature are as follows: be more than or equal to 800 DEG C, forging ratio is greater than 2；
(4) after removal forging plate surface scale, by surface cleaning, treated that plate is heat-treated, heat treatment temperature
Are as follows: 0.5-1.5h, hot rolled plate after heat treatment are 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) plate after hot rolling is subjected to heat aging processing, aging temp are as follows: 750 DEG C~800 DEG C, aging time are as follows: 20h~
100h；
(6) by heat aging treated hot rolled plate cold rolling, the intermediate anneal temperature and final annealing temperature in cold-rolled process are small
In be equal to 710 DEG C, cold rolling reduction be more than or equal to 35% to get.
2. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy material according to claim 1, feature exist
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 are Fe and impurity.
3. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy material according to claim 1, feature exist
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 are Fe and impurity.
4. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy material according to claim 1, feature exist
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 are Fe and impurity.
5. a kind of nuclear reactor fuel element involucrum FeCrAl base alloy material according to claim 1, feature exist
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 are Fe and impurity.
6. according to claim 1 to a kind of FeCrAl based alloy material of nuclear reactor fuel element involucrum described in 5 any one
The preparation method of material, it is characterised in that: including following operating procedure:
(1) FeCrAl based alloy is mixed in proportion, melting obtains ingot casting；
(2) ingot casting homo genizing annelaing at 1150 DEG C~1300 DEG C, and keep the temperature 3-10h；
(3) remove homogenizing annealing after ingot casting surface oxide skin, high temperature forging, initial forging temperature are as follows: 1050 DEG C~1150 DEG C, eventually
Forge temperature are as follows: be more than or equal to 800 DEG C, forging ratio is greater than 2；
(4) after removal forging plate surface scale, by surface cleaning, treated that plate is heat-treated, heat treatment temperature
Are as follows: 0.5-1.5h, hot rolled plate after heat treatment are 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) plate after hot rolling is subjected to heat aging processing, aging temp are as follows: 750 DEG C~800 DEG C, aging time are as follows: 20h~
100h；
(6) by heat aging treated hot rolled plate cold rolling, the intermediate anneal temperature and final annealing temperature in cold-rolled process are small
In be equal to 710 DEG C, cold rolling reduction be more than or equal to 35% to get.
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Non-Patent Citations (2)
| Title |
|---|
| Design of alumina forming FeCrAl steels for lead or lead-bismuth;Jun Lim等;《Journal of Nuclear Materials》;20120427;第441卷;图1 |
| Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors;Y. Yamamoto等,;《Journal of Nuclear Materials》;20151019;第467卷;第705页表2中C35MN合金；第705页左栏第2段 |
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