CN110284027A - A kind of zirconium-base alloy of alkali resistance water quality corrosion - Google Patents
A kind of zirconium-base alloy of alkali resistance water quality corrosion Download PDFInfo
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- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
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- C22C1/00—Making non-ferrous alloys
- C22C1/02—Making non-ferrous alloys by melting
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- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22F—CHANGING THE PHYSICAL STRUCTURE OF NON-FERROUS METALS AND NON-FERROUS ALLOYS
- C22F1/00—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working
- C22F1/16—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working of other metals or alloys based thereon
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Abstract
A kind of zirconium-base alloy of alkali resistance water quality corrosion is made of following ingredients by weight percentage: Sn:0.3-0.5, Nb:0.2-0.5, Fe:0.1-0.4, Cr:0.1-0.4, V, one of Ni, Si or multiple element: 0.004-0.02, O:0.08-0.16, surplus are Zr and other impurities.The content that the present invention passes through Sn and Nb in reduction zircaloy, add Fe, Cr element, V, one of Ni, Si or multiple element, and the contents of the alloying elements such as Fe, Cr, V, Ni, Si is adjusted to proper level, corrosion resistance of the zircaloy in lithium hydroxide aqueous solution is improved, which is placed in 70ppm water containing lithium, is 360 DEG C in temperature, pressure is that 18.6MPa corrodes 250 days, and the surrosion of zircaloy is not more than 65mg/dm2, corrosion rate is lower than 0.260mg/dm2/d。
Description
Technical field
The present invention relates to specialty alloy materials fields, and in particular to a kind of zirconium-base alloy of alkali resistance water quality corrosion.
Background technique
Zircaloy has good corrosion resistance since thermal neutron absorption cross section is small in high-temperature high pressure water and steam
Can, there is fairly good anti-neutron irradiation performance in heap, thus it is commonly used as the cladding materials of nuclear power water-cooled reactor,
It is the cladding materials that current nuclear power plant reactor uniquely uses.
In early days, cladding materials is usually made of Zr-2, Zr-4 alloy.With the further development of nuclear power, guaranteeing that core is anti-
It on the basis of answering heap safety, needs to improve the economy of nuclear reactor, reduce nuclear power operating cost, thus fuel assembly is mentioned
Long-lived phase, high burnup, zero damaged target are gone out.This means that the water side corrosion of zirconium alloy cladding aggravates, hydrogen-sucking amount increases, spoke
Increased according to time growth, pellet and cladding interaction increase and internal pressure etc., so that the service performance to zircaloy proposes more
High requirement.Develop the high request proposed to fuel can for Nuclear Power Technology, expands grinding for novel zirconium alloy in the world
Study carefully, obtains the novel zirconium alloys such as ZIRLO, E635, M5, X5A that there is more preferable corrosion resistance than Zr-4 alloy.Existing research
Show that the proportion of ingredient in existing zircaloy might not optimize on the basis of existing zircaloy in optimized scope, therefore
Alloying component and proportion, the more excellent zircaloy of corrosion resistance can be developed by adding other alloying elements also, to meet combustion
Consume the needs being continuously improved.
There is chemical addition agent due to being added in reactor-loop cooling water, thus will affect the corruption of cladding materials zircaloy
Erosion behavior, the lithium hydroxide being especially added are easy to be concentrated and significantly affect the corrosive nature of zircaloy in oxidation film, because
This, just has practical significance for the cooling hydrochemical characteristics of reactor-loop come the corrosion behavior for studying zirconium alloy cladding.But
Due to the limitation of factors, autoclave corrosion test generally is carried out to simulate corrosive nature of the zircaloy in heap in out-pile.
Out-pile corrosion test condition specifically includes that 360 DEG C of deionized waters, 360 DEG C of aqueous solutions containing lithium, 400 DEG C of steam, 500 DEG C of steam,
The zirconium alloy cladding material of experimental examination qualification can be used for presurized water reactor in 360 DEG C of aqueous solutions and 400 DEG C of steam, contain lithium at 360 DEG C
What experimental examination was qualified in aqueous solution is then more suitable for the high lithium concentration operating condition of presurized water reactor, and experimental examination closes in 500 DEG C of steam
Lattice are then applicable in boiling-water reactor.
Different chemical environment of water is different the corrosion behavior affecting laws of different zircaloys.By the study found that
When corroding in deionized water, corrosion resistance is successively deteriorated by E110 > E635 > ZIRLO > Zr-4 sequence；It is water-soluble in LiOH
When corroding in liquid, difference in the corrosion regularity and deionized water of several zircaloys, corrosion resistance by Zr-Sn-Nb alloy >
The sequence of Zr-4 > E110 is deteriorated.Meanwhile the operating experience of many years also turns out the corrosion row in E635 alloy out-pile LiOH aqueous solution
For more can corrosion condition in reactor.Therefore, corrosion behavior and out-pile LiOH for Zr-Sn-Nb system alloy, in heap
Rule when corroding in high-temperature water is close, and studying corrosion resistance of the Zr-Sn-Nb system alloy in out-pile LiOH high-temperature water has now
Sincere justice.
Summary of the invention
The purpose of the present invention is to provide a kind of alkali resistance water quality corrosion zirconium-base alloy, by adjusting, optimization zircaloy
Component, content, proportion, corrosion resistance of the zirconium-base alloy outside 360 DEG C of water-water reactors containing lithium under the conditions of corrosion test is improved, to meet
The needs that burnup is continuously improved, further develop for nuclear power plant reactor and provide more excellent zircaloy.
In the prior art, element S n is capable of the α phase of stabilised zirconia, it is ensured that alloy has excellent corrosion resistance and good
Mechanical property；Element nb is capable of the β phase of stabilised zirconia, has higher invigoration effect to zirconium, it is ensured that alloy has excellent corrosion-resistant
Performance and good mechanical property；Element of Fe, Cr, V, Si can improve alloy corrosion resistance and mechanical property, it is ensured that alloy tool
There is excellent corrosion resistance；Element Ni can improve alloy corrosion resistance energy, it is ensured that alloy has excellent corrosion resistance；
Element O is capable of the α phase of stabilised zirconia, and addition oxygen can improve yield strength in alloy, and alloy has enough mechanical performances and resists compacted
It is denaturalized energy.
Although total content of the microelement in zircaloy is no more than the 5% of zircaloy, the selection of microelement contains
Amount, ratio play a crucial role corrosion resistance of the zircaloy as cladding materials under different etching conditions.Closely
Domestic and foreign scholars have carried out a large amount of research to the content of microelement over year.
(Zhou Bangxin, Li Qiang is yellow strong etc., research [J] core that water chemistry influences Corrosion Resistance of Zirconium Alloys by Zhou Bangxin etc.
Power engineering, 2000,21 (5): 439-447.) it points out when studying Corrosion Resistance of Zirconium Alloys, Nb and Sn, Fe, Cr content are made
When difference collocation, material corrosion performance variation degree shows huge difference.When Sn, Nb individualism to zircaloy in LiOH water
Corrosion resistance in solution be it is unfavorable, only can just play inhibition after they match by a certain percentage and add sufficient amount
The illeffects of LiOH accelerated corrosion.Yueh etc. (Yueh H.K., Kesterson R.L., Comstock R.J., et al.,
Improved ZIRLOTM cladding performance through chemistry and process
modifications[C].Zirconium in the Nuclear Industry:Fourteenth International
Symposium, ASTM STP 1467,2004, PP.330-346.) report the result of study for optimizing ZIRLO alloying component, heap
Outer autoclave corrosion test shows to reduce Sn content to improvement ZIRLO alloy corrosion resistance in 360 DEG C of LiOH aqueous solutions
Effect is most significant, but cannot be too low, otherwise will appear accelerated corrosion.It, can be in addition, when the dosage of Nb, V, Ni, Si are excessive
Zircaloy is adversely affected to a certain extent, such as sensitive to heat treatment process.
It can be seen that influence of the microelement to Corrosion Resistance of Zirconium Alloys is extremely complex, depend on alloying element type,
The influence of many factors such as proportion and water chemistry condition.
Moreover, there is also influences on corrosive nature for the second phase particles of zircaloy.
At zircaloy corrosion initial stage, one layer of fine and close oxidation film of Surface Creation, predominantly cube, the isostructural oxidation in four directions
Zirconium.With the progress of corrosion, oxide growth, cube, tetragonal phase zirconium oxide gradually change to monocline phase zircite, oxidation film
Consistency reduces, and corrosion is accelerated.In corrosion process, zirconium base body aoxidizes zircaloy prior to second phase particles.Thus, second
Phase particle can be embedded in oxidation film and as thickening for oxidation film is oxidized in oxidation film, so that oxidation film is had an impact,
Corrosion rate is caused to change.
The P.B. ratio that oxidation film is formed is 1.56, thus oxidation film formed after can generate compression, the second phase grain inside it
The insertion of son will certainly be such that the compression in the oxidation film around second phase particles increases.Since tetragonal phase zirconium oxide is to monoclinic phase
The transition process of zirconium oxide is equally the process of volume expansion, thus compression increase caused by the insertion of second phase particles will have
Conducive to the stability for maintaining tetragonal phase zirconium oxide, increase the consistency of oxidation film.For this angle, quantity is more, it is tiny,
Equally distributed second phase particles are conducive to improve the corrosion resistance of zircaloy, and quantity few, coarse, uneven distribution the
Secondary phase particle be easy to cause oxidation film internal compressive stress uneven, causes some regions preferentially to be corroded, is further exacerbated by partial zones
The defects of domain stress is concentrated, and generates hole, crackle too early, destroys the protectiveness of oxidation film.In addition, second phase particles with
Thickening for oxidation film be oxidized in oxidation film, volume expands, and generates in the oxidation film around second phase particles
Circumferential tensile stress promotes surrounding zirconium oxide to monocline phase transition, or is changed from columnar crystal structure to isometric crystal structure, draws
Corrosion rate is played to increase.As one can imagine second phase particles size is bigger or the reunion of second phase particles is more serious, by second
The effect caused by phase particle aoxidizes is more serious.
In conclusion either cause the increased angle of oxidation film internal stress from second phase particles insertion, or from second
Promote angle of the zirconium oxide to monocline phase transition when phase particle aoxidizes, it is tiny, area fraction is high, equally distributed second phase
Particle is low with coarse, area fraction, uneven distribution second phase particles are compared, and can more maintain the stability of oxidation film.
Inventor is by the theoretical researches of many years and ex-reactor experiment, on the basis of existing technology, further decrease Sn and
The content of Nb element adds Fe and Cr element, and controls Fe and Nb, the content ratio of Fe and Cr, obtains a kind of more optimal resistance to
The zirconium-base alloy of alkaline water quality corrosion.
Specifically, the present invention is achieved through the following technical solutions:
A kind of zirconium-base alloy of alkali resistance water quality corrosion is made of following ingredients by weight percentage: Sn:0.3-
0.5, Nb:0.2-0.5, Fe:0.1-0.4, Cr:0.1-0.4, one of V, Ni, Si or multiple element: 0.004-0.02, O:
0.08-0.16, surplus are Zr and other impurities.
The zircaloy of said components not only has a lower Sn and Nb content, but also by adjusting addition Fe and Cr element,
V, one of Ni, Si or multiple element, so that the zircaloy is compared to the property that the alkali resistance water quality of traditional zircaloy is corroded
It can be more preferable.In some embodiments, which is placed in 70ppm water containing lithium, is 360 DEG C in temperature, pressure 18.6MPa
The surrosion of corrosion 250 days, the zircaloy is not more than 65mg/dm2, corrosion rate is lower than 0.260mg/dm2/d；In part
In embodiment, by controlling the content ratio of Fe and Nb, Fe and Cr, make caused by the zircaloy in conjunction with the content of said components
The more of second phase particles, partial size are more tiny, more uniform in the distribution of Zr alloy surface, are more able to maintain that oxidation film
The zircaloy is placed in 70ppm water containing lithium by stability, is 360 DEG C in temperature, and pressure is that 18.6MPa corrodes 250 days, and zirconium closes
The surrosion only 47mg/dm of gold2, corrosion rate only 0.188mg/dm2/ d greatly reduces the corrosion rate of zircaloy, and right
For Zr-Sn-Nb system alloy, the corrosion behavior in heap is close with rule when corroding in out-pile LiOH high-temperature water, and then says
The bright zircaloy may greatly have higher corrosion resistance in applying in heap, to meet the need that burnup is continuously improved at this stage
It asks.
Further, the zirconium-base alloy of the alkali resistance water quality corrosion is made of following component by weight percentage:
Sn:0.3-0.4, Nb:0.35-0.5, Fe:0.3-0.4, Cr:0.1-0.2, one of V, Ni, Si or multiple element: 0.004-
0.02, O:0.1-0.15, surplus is Zr and other impurities.
Further, the zirconium-base alloy of the alkali resistance water quality corrosion is made of following component by weight percentage:
Sn:0.3-0.4, Nb:0.35-0.4, Fe:0.35-0.36, Cr:0.14-0.15, Ni:0.01-0.02, Si:0.01-0.02, O:
0.1-0.15, surplus are Zr and other impurities.
Further, the zirconium-base alloy of the alkali resistance water quality corrosion is made of following component by weight percentage:
Sn:0.3-0.4, Nb:0.35-0.4, Fe:0.35-0.36, Cr:0.14-0.15, V:0.005-0.01, O:0.1-0.15, surplus
For Zr and other impurities.
Further, the zirconium-base alloy of the alkali resistance water quality corrosion is made of following component by weight percentage:
Sn:0.3-0.4, Nb:0.35-0.4, Fe:0.35-0.36, Cr:0.14-0.15, Si:0.004-0.01, O:0.1-0.15, it is remaining
Amount is Zr and other impurities.
It is further preferred that the zirconium-base alloy of the alkali resistance water quality corrosion, by weight percentage, by following component group
At: Sn:0.30, Nb:0.36, Fe:0.36, Cr:0.14, Ni:0.02, Si:0.01, O:0.11, surplus are Zr and other impurities.
As a preferred embodiment of the present invention, the content ratio of Fe and Cr are 2~2.7:1, are found through experiments that,
When the content ratio of Fe and Cr is less than 2, the corrosion rate of zircaloy and surrosion are not reached requirement.It is further preferred that
The content ratio of the Fe and Cr is 2.4~2.7:1, and still further preferably, the content ratio of the Fe and Cr are 2.57.
Further, the content ratio of Nb and Fe is 1~1.5:1.It is found through experiments that, when the content ratio of Nb and Fe are big
When 1.5, required requirement is not achieved in the corrosion rate of zircaloy and surrosion.It is further preferred that the content of Nb and Fe
Ratio is 1.
Further, pass through the second phase grain of above-mentioned microcomponent type, content and the obtained zircaloy of proportion relation
The area fraction of son is 4%~6%.Wherein, the area fraction refers to face shared by second phase particles in a certain field of view
The long-pending ratio with the visual field gross area, area fraction is bigger to represent the more of second phase particles in unit area.The prior art
In, the area fraction of reference alloy Zr-4 is 1.15%, it can be seen that, second phase particles number in the obtained zircaloy of the present invention
Amount is more than reference alloy Zr-4.
Further, the diameter mean value of the second phase particles of the zircaloy is 30~40nm, the of reference alloy Zr-4
The diameter mean value of Secondary phase particle is 160nm, illustrates that zircaloy disclosed in this invention is capable of forming the second more tiny phase grain
Son.
Compared with prior art, the present invention having the following advantages and benefits:
1, the present invention provides a kind of zirconium-base alloys of alkali resistance water quality corrosion, are contained by reducing Sn and Nb in zircaloy
Amount adds Fe, Cr element, one of V, Ni, Si or multiple element, and adjusts containing for the alloying elements such as Fe, Cr, V, Ni, Si
Amount improves corrosion resistance of the zircaloy in lithium hydroxide aqueous solution, which is placed in 70ppm and is contained to proper level
It is 360 DEG C in temperature in lithium water, pressure is that 18.6MPa corrodes 250 days, and the surrosion of zircaloy is not more than 65mg/dm2, rotten
It loses rate and is lower than 0.260mg/dm2/d；
2, the present invention content ratio of content ratio and Fe and Cr to Fe in zirconium-base alloy and Nb is controlled, Fe with
The content ratio of Cr is that the content ratio of 2~2.7:1, Nb and Fe are 1~1.5:1, is selected in conjunction with type, the content of alloying element
Select so that the more of second phase particles caused by the zircaloy, partial size are more tiny, Zr alloy surface distribution more
Uniformly, it is more able to maintain that the stability of oxidation film, which is placed in 70ppm water containing lithium, be 360 DEG C in temperature, pressure
For 18.6MPa corrosion 250 days, the surrosion of zircaloy only 47mg/dm2, corrosion rate only 0.188mg/dm2/ d, substantially reduces
The corrosion rate of zircaloy, illustrates that the zircaloy may greatly have higher corrosion resistance in applying in heap, to meet
The demand that burnup is continuously improved at this stage.
Detailed description of the invention
Attached drawing described herein is used to provide to further understand the embodiment of the present invention, constitutes one of the application
Point, do not constitute the restriction to the embodiment of the present invention.In the accompanying drawings:
Fig. 1 is the SEM scanning electron microscope (SEM) photograph of the second phase particles of zircaloy in the embodiment of the present invention 1；
Fig. 2 is the area fraction and diameter mean value of the second phase particles of zircaloy in the embodiment of the present invention 1；
Fig. 3 is the SEM scanning electron microscope (SEM) photograph of the second phase particles of zircaloy in the embodiment of the present invention 2；
Fig. 4 is the area fraction and diameter mean value of the second phase particles of zircaloy in the embodiment of the present invention 2；
Fig. 5 is the SEM scanning electron microscope (SEM) photograph of the second phase particles of zircaloy in the embodiment of the present invention 3；
Fig. 6 is the area fraction and diameter mean value of the second phase particles of zircaloy in the embodiment of the present invention 3；
Fig. 7 is the SEM scanning electron microscope (SEM) photograph of the second phase particles of reference alloy Zr-4 zircaloy；
Fig. 8 is the area fraction and diameter mean value of the second phase particles of reference alloy Zr-4 zircaloy.
Specific embodiment
To make the objectives, technical solutions, and advantages of the present invention clearer, below with reference to embodiment and attached drawing, to this
Invention is described in further detail, and exemplary embodiment of the invention and its explanation for explaining only the invention, are not made
For limitation of the invention.
The present invention be used to prepare alkali resistance water quality corrosion zirconium-based alloy material technique specifically includes the following steps:
(1) each component in zircaloy is subjected to ingredient according to design ingredient；
(2) melting is carried out in vacuum consumable electrode arc furnace, and alloy cast ingot is made；
(3) alloy cast ingot is forged into the blank material of required shape in 900 DEG C~1200 DEG C of β phase region；
(4) the β phase region homogeneous heating by blank material at 1000 DEG C~1200 DEG C, and be quenched；
(5) quenched blank material is subjected to hot-working 600 DEG C~700 DEG C of alpha phase zone；
(6) blank material after hot-working is cold worked, and in 560 DEG C~650 DEG C progress intermediate annealings；
(7) stress relief annealing or recrystallization annealing processing are carried out in 480 DEG C~620 DEG C, obtain the zircaloy material
Material.
Three kinds of Zirconium alloy materials that 1-3 according to embodiments of the present invention is provided, the Zirconium alloy material of comparative example 4 and existing
Zr-4 alloy in technology, N36 alloy carry out the test of out-pile corrosive nature.The corrosion test carries out in autoclave, rotten
Erosion condition is to immerse Li containing 70ppm+LiOH solution in, corrode under conditions of temperature is 360 DEG C, pressure is 18.6MPa
250 days.
Table 1 give the zircaloy constituent of 1-3 of the embodiment of the present invention, the zircaloy constituent of comparative example 4 and
Their corrosion rates under above-mentioned etching condition；5* is the composition of Zr-4 alloy and the corrosion speed under identical etching condition
Rate, the composition and the corrosion rate under identical etching condition that 6* is N36 alloy.
Table 1:
It can be seen that corrosion speed of the zircaloy of 1-3 of the embodiment of the present invention in 360 DEG C of water containing lithium from the data of table 1
Rate is lower than 0.260mg/dm2/ d, far smaller than Zr-4 alloy, hence it is evident that better than the N36 alloy researched and developed in recent years, illustrate such alloy
Corrosion resistance in out-pile LiOH high-temperature water is substantially better than existing Zr-4 alloy and N36 alloy.Also, for Zr-Sn-Nb
It is for alloy, the corrosion behavior in heap is close with rule when corroding in out-pile LiOH high-temperature water, further relates to the zircaloy
May greatly have higher corrosion resistance in applying in heap, can satisfy the demand that burnup is continuously improved at this stage.
From the data of table 1 can also be seen that inventor by component ratio the study found that control zirconium-base alloy in Fe
Content ratio with Cr is 2~2.7:1, and the content ratio for further controlling Nb and Fe is that 1~1.5:1 can further increase zirconium
The anticorrosion effect of alloy.In comparative example 4, the mass ratio of Fe in zircaloy and Cr is adjusted to the quality of 1:2.25, Nb and Fe
Than being adjusted to 1.8:1, so that by weight percentage, even if it is 0.3-0.5, Nb 0.2-0.5, Fe that zircaloy ingredient, which meets Sn,
For 0.1-0.4, Cr 0.1-0.4, but corrosion rate of the zircaloy of comparative example 4 in high temperature water containing lithium reaches 0.374mg/
dm2/ d, although achieving significant progress compared to Zr-4 alloy, anticorrosion effect is not so good as N36 alloy.Thus illustrate, fit
When Fe and Cr, Nb and Fe can further promote corrosion resistant of the zircaloy in high temperature water containing lithium to special ratios in adjustment component
Corrosion.
Through a large number of experiments the study found that above-mentioned preferred proportion range enables to the second phase grain formed on zircaloy
The more, partial size of son is smaller, more uniform in the distribution of Zr alloy surface, so be able to maintain that the stability of oxidation film with
Improve the corrosion resistance of zircaloy.
Fig. 1-6 shows the SEM scanning electron microscope (SEM) photograph and second phase particles of the second phase particles of zircaloy in embodiment 1-3
Area fraction and diameter mean value.Wherein, in SEM scanning electron microscope (SEM) photograph, HV indicates that beam voltage, mag indicate times magnification
Number, WD represent operating distance, and det indicates detector type.Second from the zircaloy that Fig. 1-8 can be seen that embodiment 1-3
Phase particle is in the characteristics of quantity is more, partial size is small and is evenly distributed, and the area fraction of three kinds of alloys is between 4.22% to 5.46%
Between, the quantity of second phase particles is significantly more than the second phase particles quantity of reference alloy Zr-4；Meanwhile three kinds of alloys is straight
Diameter mean value is respectively less than 35.3nm, and the partial size of second phase particles is significantly less than the partial size of the second phase particles of reference alloy Zr-4.
In conjunction with table 1 it is found that the mass ratio that the mass ratio of Fe and Cr are adjusted to 2.57:1, Nb and Fe is adjusted in the zircaloy of embodiment 2
1:1, herein under preferred ratio, the area fraction of embodiment 2 is 5.46%, and diameter mean value is 35.3nm, compared to embodiment 1
With the area fraction of embodiment 3 is bigger, diameter mean value is smaller, the corrosion rate in high temperature water containing lithium is only 0.188mg/
dm2The corrosion rate of existing N36 alloy is reduced 43.5% by/d.
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 (10)
1. a kind of zirconium-base alloy of alkali resistance water quality corrosion, which is characterized in that by weight percentage, be made of following ingredients:
Sn:0.3-0.5, Nb:0.2-0.5, Fe:0.1-0.4, Cr:0.1-0.4, one of V, Ni, Si or multiple element: 0.004-
0.02, O:0.08-0.16, surplus is Zr and other impurities.
2. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 1, which is characterized in that by weight percentage
Meter, is made of: one in Sn:0.3-0.4, Nb:0.35-0.5, Fe:0.3-0.4, Cr:0.1-0.2, V, Ni, Si following component
Kind or multiple element: 0.004-0.02, O:0.1-0.15, surplus are Zr and other impurities.
3. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 2, which is characterized in that by weight percentage
Meter, is made of: Sn:0.3-0.4, Nb:0.35-0.4, Fe:0.35-0.36, Cr:0.14-0.15, Ni:0.01- following component
0.02, Si:0.01-0.02, O:0.1-0.15, surplus are Zr and other impurities.
4. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 2, which is characterized in that by weight percentage
Meter, is made of: Sn:0.3-0.4, Nb:0.35-0.4, Fe:0.35-0.36, Cr:0.14-0.15, V:0.005- following component
0.01, O:0.1-0.15, surplus is Zr and other impurities.
5. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 2, which is characterized in that by weight percentage
Meter, is made of: Sn:0.3-0.4, Nb:0.35-0.4, Fe:0.35-0.36, Cr:0.14-0.15, Si:0.004- following component
0.01, O:0.1-0.15, surplus is Zr and other impurities.
6. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to any one of claims 1 to 5, which is characterized in that
The content ratio of Fe and Cr is 2~2.7:1.
7. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 6, which is characterized in that the content of Nb and Fe
Ratio is 1~1.5:1.
8. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 7, which is characterized in that by the zircaloy
It is placed in Li containing 70ppm+LiOH in, temperature be 360 DEG C, pressure be 18.6MPa corrode 250 days, the corrosion of the zircaloy
Weight gain is not more than 65mg/dm2。
9. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 7, which is characterized in that the zircaloy
The area fraction of second phase particles is 4%~6%.
10. a kind of zirconium-base alloy of alkali resistance water quality corrosion according to claim 7, which is characterized in that the zircaloy
Second phase particles diameter mean value be 30~40nm.
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