CN106957971A - A kind of compressed water reactor nuclear power station-service zircaloy and preparation method thereof - Google Patents
A kind of compressed water reactor nuclear power station-service zircaloy and preparation method thereof Download PDFInfo
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- CN106957971A CN106957971A CN201710388915.8A CN201710388915A CN106957971A CN 106957971 A CN106957971 A CN 106957971A CN 201710388915 A CN201710388915 A CN 201710388915A CN 106957971 A CN106957971 A CN 106957971A
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- zircaloy
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- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C16/00—Alloys based on zirconium
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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
- C22F1/002—Changing the physical structure of non-ferrous metals or alloys by heat treatment or by hot or cold working by rapid cooling or quenching; cooling agents used therefor
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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
- C22F1/18—High-melting or refractory metals or alloys based thereon
- C22F1/186—High-melting or refractory metals or alloys based thereon of zirconium or alloys based thereon
Abstract
The invention discloses a kind of compressed water reactor nuclear power station-service zircaloy and preparation method thereof, solve how optimized alloy element composition and the problem of match for developing decay resistance more excellent zircaloy.Weight percentage of the present invention, is made up of following ingredients：Sn：0.30 0.80, Nb：0.20 0.60, Fe：0.20 0.45, Mo and/or Cu：0.01 0.15, O：0.06 0.18, surplus is Zr and other impurity.The present invention is on the basis of Zr Sn Nb alloys, with the addition of other is used to improve the composition of alloy property, and have selected appropriate constituent content, the alloy property that the present invention is provided meets requirement of the power producer high burnup to core structural material, the general corrosion resistance performance in out-pile pure water and lithium hydroxide aqueous solution is improved, the resistance to Nodular Corrosion in high-temperature steam is improved.The alloy of the present invention is used with more excellent resistance to uniform Nodular Corrosion, higher creep resistant and fatigue properties, Flouride-resistani acid phesphatase growth performance in reactor.
Description
Technical field
The present invention relates to specialty alloy materials technical field, and in particular to a kind of compressed water reactor nuclear power station-service zircaloy, and public
The preparation method of the zircaloy is opened.
Background technology
Zircaloy is small due to thermal neutron absorption cross section, while there is good corrosion resistance 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 is uniquely used.
With the further development of nuclear power, it is necessary to improve nuclear reactor on the basis of reactor safety is ensured
Economy, reduction nuclear power operating cost, thus propose to fuel assembly long-lived phase, high burnup, zero damaged target.This meaning
Water side corrosion exacerbation, hydrogen-sucking amount increase, exposure time growth, pellet and the cladding interaction for zirconium alloy cladding increase and interior
Pressure rise etc., so that the performance to zircaloy proposes higher requirement.
Develop the high request proposed to fuel can for Nuclear Power Technology, grinding for novel zirconium alloy is expanded in the world
Study carefully, obtain the novel zirconium alloys such as ZIRLO, E635, M5, the X5A that there is more preferable decay resistance than Zr-4 alloy.Study
Show, the proportioning of composition might not be in optimized scope in existing zircaloy, the optimized alloy on the basis of existing zircaloy
Composition proportion or the other alloying elements of addition can also develop the more excellent zircaloy of decay resistance, to meet burnup not
The need for disconnected raising.
The content of the invention
The technical problems to be solved by the invention are：How optimized alloy element composition and match for developing corrosion resistant
Corrosion can more excellent zircaloy the problem of, it is therefore intended that there is provided a kind of compressed water reactor nuclear power station-service zircaloy and its preparation side
Method, its zircaloy being made has good corrosion resistance.
The present invention is achieved through the following technical solutions：
A kind of compressed water reactor nuclear power station-service zircaloy, weight percentage is made up of following ingredients：
Sn：0.30-0.80, Nb：0.20-0.60, Fe：0.20-0.45, Mo and/or Cu：0.01-0.15, O：0.09-
0.18, surplus is Zr and other impurity.
For the zircaloy for nuclear reactor cladding materials, the decay resistance of zircaloy be overriding concern because
Element, needs to consider when production cost and machinability are selection alloying elements on this basis.Accordingly, it would be desirable to which research is every in detail
The consumption of every kind of alloying element in influence and alloy system of a kind of alloying element to corrosion resistance, mechanical performance and creep behaviour
Scope.
Wherein, zirconium (Zr)：In view of the consideration to neutron economy, present invention selection neutron absorption cross-section is smaller (0.185b)
Zirconium as matrix element, while being also contemplated for being added to the neutron absorption cross-section situation of other alloying elements in zirconium base body.
Tin (Sn)：Tin is capable of the α phases of stabilised zirconia, increases its intensity, and can offset illeffects of the nitrogen to corrosion.When tin is used
When measuring very few, it is impossible to reach required effect.Sn addition content is 0.3-0.8% (percentage by weight) in the present invention, it is ensured that
Alloy has excellent decay resistance and good mechanical property.
Niobium (Nb)：Niobium is capable of the β phases of stabilised zirconia, there is higher invigoration effect to zirconium.When niobium consumption is excessive, to heat treatment
It is sensitive.Nb adds content at 0.2-0.6% (percentage by weight) in the present invention, ensure that alloy has excellent corrosion resistance
Can be with good mechanical property.
Iron (Fe)：Iron can improve alloy corrosion resistance and mechanical property, but iron consumption is excessive or very few can all produce not
The influence of profit.The content that Fe is added in the present invention ensure that alloy has excellent at 0.2-0.45% (percentage by weight)
Decay resistance.
Molybdenum (Mo)：Molybdenum is very high to the strengthening effect of zirconium, but declines plasticity, the ZrMo that Mo and Zr is generated2Second in base
Integrated distribution is unfavorable to decay resistance in body, but fine to the dispersion-strengthened effect of zircaloy, shows Mo zircaloys to be contained
Corrosion resistance is relevant with the microscopic structure of matrix.In the present invention Mo add content at 0.01-0.15% (percentage by weight),
It ensure that alloy has excellent decay resistance.
Copper (Cu)：Copper can improve alloy corrosion resistance energy, but copper consumption can excessively have adverse effect on.In the present invention
The content of Cu additions ensure that alloy has excellent decay resistance at 0.01-0.15% (percentage by weight).
Oxygen (O)：Oxygen, which is capable of addition oxygen in the α phases of stabilised zirconia, alloy, can improve yield strength.What O was added in the present invention contains
Amount ensure that alloy has enough mechanical performance and creep-resistant property at 0.09-0.18% (percentage by weight).Oxygen content
Increase, greatly reduce the control difficulty in material processing.
Tin addition is typically, in 0.7-1.6%, such as in CN01141590.8, to be disclosed in this document in the prior art
Prepared and recorded for containing for nuclear fuel cladding in niobium zirconium alloy, but this document using alloying elements such as Zr, Sn, Nb, Fe, Mo
" when the consumption of tin is reduced to increase corrosion resistance, other alloy forming elements of exchange need to be added to replace tin to keep strong
Degree ".Thus, industry technical staff is when reducing the consumption of tin, it will usually finds other metallic elements and replaces tin to increase by force
Degree.But, if by the way of increasing intensity using finding other metallic elements replacement tin, composition can be caused more complicated, into
This increase, technique is more complicated, and adds the requirement needed for effect after other elements can not necessarily reach.The present invention passes through it
The ratio optimization of his composition, makes the Sn in the present invention add content and is reduced to 0.3-0.8%, still ensure that alloy has
There are excellent decay resistance and good mechanical property, effect is very notable.
The present invention is on the basis of Zr-Sn-Nb alloys, and with the addition of other is used to improve the elemental composition of alloy property, and selects
Selected appropriate constituent content, zircaloy of the present invention have more excellent resistance to uniform Nodular Corrosion, with compared with
High creep resistant and fatigue properties, Flouride-resistani acid phesphatase growth performance.Thus, the alloy property that the present invention is provided meets power producer
Requirement of the high burnup to core structural material.Also, by the testing inspection result in embodiment, by this original
Product prepared by type alloy improves the general corrosion resistance performance in out-pile pure water and lithium hydroxide aqueous solution, improves in height
Resistance to Nodular Corrosion in warm steam.It is considered that these alloys are used in reactor has more excellent resistance to uniform furuncle
Shape corrosive nature, higher creep resistant and fatigue properties, Flouride-resistani acid phesphatase growth performance.
Further, weight percentage, is made up of following ingredients：
Sn：0.30-0.50, Nb：0.40-0.60, Fe：0.20-0.45, Mo and/or Cu：0.02-0.15, O：0.09-
0.18, surplus is Zr and other impurity.
Further, weight percentage, is made up of following ingredients：
Sn：0.30-0.50, Nb：0.40-0.60, Fe：0.24-0.36, Mo：0.04-0.12, O：0.09-0.18, surplus
For Zr and other impurity.
Further, weight percentage, is made up of following ingredients：
Sn：0.35-0.50, Nb：0.45-0.55, Fe：0.24-0.36, Mo：0.04-0.12, O：0.09-0.18, surplus
For Zr and other impurity.
As another preferred embodiment, weight percentage is made up of following ingredients：
Sn：0.60-0.80, Nb：0.20-0.40, Fe：0.20-0.45, Mo：0.02-0.15, O：0.09-0.18, surplus
For Zr and other impurity.
One of which preferred arrangement during Mo and Cu, weight percentage, by following ingredients group are added simultaneously
Into：
Sn：0.60-0.80, Nb：0.20-0.40, Fe：0.25-0.37, Mo：0.02-0.12, Cu：0.02-0.08, O：
0.09-0.18, surplus is Zr and other impurity.
Further, weight percentage, is made up of following ingredients：
Sn：0.60-0.75, Nb：0.25-0.35, Fe：0.25-0.37, Mo：0.02-0.12, Cu：0.02-0.08, O：
0.09-0.18, surplus is Zr and other impurity.
Another preferred arrangement during Mo and Cu is added simultaneously, and weight percentage is made up of following ingredients：
Sn：0.60-0.80, Nb：0.25-0.35, Fe：0.25-0.37, Mo：0.02-0.12, Cu：0.02-0.08, O：
0.09-0.15, surplus is Zr and other impurity.
A kind of preparation method of compressed water reactor nuclear power station-service zircaloy, including：
(1) dispensing is carried out according to above-mentioned proportioning；
(2) melting is carried out in vacuum consumable electrode arc furnace, alloy cast ingot is made；
(3) alloy cast ingot is forged into the blank material of required shape in β phase regions；
(4) by blank material in β phase region homogeneous heatings, and Quenching Treatment is carried out；
(5) blank material after quenching is subjected to hot-working in alpha phase zone；
(6) blank material after hot-working is subjected to cold working, and carries out intermediate annealing；
(7) stress relief annealing or recrystallization annealing processing are carried out, the Zirconium alloy material is obtained.
Wherein, the forging temperature of β phase regions is β phase regions in 900 DEG C~1200 DEG C, the step (4) in the step (3)
Heating-up temperature is that the hot processing temperature of alpha phase zone in 1000 DEG C~1200 DEG C, the step (5) is 600 DEG C~700 DEG C, the step
Suddenly the temperature of intermediate annealing is the place of stress relief annealing or recrystallization annealing in 560 DEG C~650 DEG C, the step (7) in (6)
It is 480 DEG C~620 DEG C to manage temperature.
In the prior art, such as in the higher zircaloy of Nb contents, including ZIRLO, M5 and N36 etc., when raising hot-working
Temperature after, super saturated solid solution Nb in the roughening and uneven distribution and alloy substrate due to the second phase can cause corrosion-resistant
Degradation, thus the present invention uses " low temperature process technique ", i.e., added using the low temperature of relatively low hot processing temperature and annealing temperature
Work technique results in the second phase constitution of small and dispersed, so as to greatly improve the decay resistance and mechanical property of alloy.
Thus, the Zirconium alloy material prepared by above-mentioned constituent and processing technology has equiaxial α-Zr crystal grain and uniform
The microstructure of the tiny second phase particles composition of distribution, can guarantee that has excellent make in reactor core harsh environment
Use performance.That is, alloy of the present invention obtains the second phase of small and dispersed distribution after being processed through low temperature process, improve the power of alloy
Learn performance (such as creep and fatigue behaviour) and Flouride-resistani acid phesphatase growth performance.
The present invention compared with prior art, has the following advantages and advantages：
1st, alloy of the invention all shows good decay resistance when corroding under the conditions of above-mentioned 3 kinds of water chemistry, bright
It is aobvious to be better than N36 alloys；
2nd, alloy of the present invention obtains the second phase of small and dispersed distribution after being processed through low temperature process, improves the power of alloy
Learn performance and Flouride-resistani acid phesphatase growth performance；
3rd, the present invention is reducing Sn addition content, and in the case where being substituted without other compositions, according to
So it ensure that alloy has excellent decay resistance and good mechanical property, effect is very notable.
Brief description of the drawings
Accompanying drawing described herein is used for providing further understanding 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 heterogeneous microstructure figure of the alloy of serial number 1 in embodiment under different amplification
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
A kind of compressed water reactor nuclear power station-service zircaloy, its concrete composition is as shown in table 1.Wherein, 9* and 10* are respectively that Zr-4 is closed
Gold and N36 alloys.
Table 1
| Alloy sequence number | Sn | Nb | Fe | Mo | Cu | Cr | O | Zr and other impurity |
| 1 | 0.40 | 0.50 | 0.30 | 0.05 | - | - | 0.11 | Surplus |
| 2 | 0.70 | 0.30 | 0.35 | 0.08 | 0.05 | - | 0.11 | Surplus |
| 3 | 0.31 | 0.21 | 0.20 | 0.01 | 0.02 | - | 0.09 | Surplus |
| 4 | 0.79 | 0.60 | 0.44 | 0.09 | 0.08 | - | 0.18 | Surplus |
| 5 | 0.38 | 0.31 | 0.32 | - | 0.07 | - | 0.12 | Surplus |
| 6 | 0.70 | 0.51 | 0.37 | 0.08 | - | - | 0.11 | Surplus |
| 7 | 0.38 | 0.27 | 0.32 | - | 0.03 | - | 0.15 | Surplus |
| 8 | 0.68 | 0.47 | 0.25 | 0.05 | - | - | 0.10 | Surplus |
| 9* | 1.27 | - | 0.22 | - | - | 0.12 | 0.09 | Surplus |
| 10* | 1.00 | 0.99 | 0.30 | - | - | - | 0.12 | Surplus |
Using the composition in above-mentioned table 1, alloy is prepared using following methods, specific preparation method is：
(1) each component in zircaloy is subjected to dispensing according to design composition；
(2) melting is carried out in vacuum consumable electrode arc furnace, 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 regions；
(4) the β phase region homogeneous heatings by blank material at 1000 DEG C~1200 DEG C, and carry out Quenching Treatment；
(5) blank material after quenching is subjected to hot-working 600 DEG C~700 DEG C of alpha phase zone；
(6) blank material after hot-working is subjected to cold working, and intermediate annealing is carried out at 560 DEG C~650 DEG C；
(7) stress relief annealing or recrystallization annealing processing are carried out in 480 DEG C~620 DEG C, the zircaloy material is obtained
Material.
The present invention detects that detection project is included in 360 DEG C of pure water to matching the alloy material being made in above-mentioned table 1
Corrosion rate after corroding 200 days, the corrosion rate after corroding 200 days in 360 DEG C of water containing lithium is corroded in 400 DEG C of steam
Corrosion rate after 200 days, detection concrete outcome is as shown in table 2.
Wherein, the qualified zirconium alloy cladding material of experimental examination can be used for pressure water in 360 DEG C of aqueous solution and 400 DEG C of steam
Heap, what experimental examination was qualified in 360 DEG C of aqueous solution containing lithium is then more suitable for the high lithium concentration operating mode of presurized water reactor, and in 500 DEG C of steamings
Experimental examination is qualified in vapour is then applicable in boiling-water reactor.
Table 2
Pass through above-mentioned table 2：Alloy of the present invention all shows good resistance to when corroding under the conditions of above-mentioned 3 kinds of water chemistry
Corrosive nature, corrosion rate of the alloy in 360 DEG C/18.6MPa pure water and the 360 DEG C/18.6MPa LiOH aqueous solution is substantially excellent
In Zr-4 and N36 alloys, the corrosion rate in 400 DEG C/10.3MPa steam is better than N36 alloys, suitable with Zr-4 alloys.Cause
And, alloy material provided by the present invention is shown well in 360 DEG C of pure water, lithium hydroxide aqueous solution and 400 DEG C of steam
Decay resistance.
Present invention employs preferred Sn, Nb, Fe, Mo, Cu composition range, between alloying element within this range
Interaction, with reference to low temperature process technique, generates effect unexpected in advance.This effect is mainly manifested in two sides
Face：1) alloy of the present invention all shows good decay resistance when corroding under the conditions of above-mentioned 3 kinds of water chemistry, hence it is evident that be better than
N36 alloys；2) alloy component range of the invention obtains the second phase of small and dispersed distribution after being processed through low temperature process, improves
The mechanical property of alloy (such as creep and fatigue behaviour) and Flouride-resistani acid phesphatase growth performance.
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 modifications, equivalent substitutions and improvements done etc. all should be included
Within protection scope of the present invention.
Claims (10)
1. a kind of compressed water reactor nuclear power station-service zircaloy, it is characterised in that：Weight percentage, is made up of following ingredients：
Sn：0.30-0.80, Nb：0.20-0.60, Fe：0.20-0.45, Mo and/or Cu：0.01-0.15, O：0.09-0.18, it is remaining
Measure as Zr and other impurity.
2. a kind of compressed water reactor nuclear power station-service zircaloy according to claim 1, it is characterised in that percentage composition by weight
Meter, is made up of following ingredients：
Sn：0.30-0.50, Nb：0.40-0.60, Fe：0.20-0.45, Mo and/or Cu：0.02-0.15, O：0.09-0.18, it is remaining
Measure as Zr and other impurity.
3. a kind of compressed water reactor nuclear power station-service zircaloy according to claim 2, it is characterised in that percentage composition by weight
Meter, is made up of following ingredients：
Sn：0.30-0.50, Nb：0.40-0.60, Fe：0.24-0.36, Mo：0.04-0.12, O：0.09-0.18, surplus is Zr
And other impurity.
4. a kind of compressed water reactor nuclear power station-service zircaloy according to claim 3, it is characterised in that percentage composition by weight
Meter, is made up of following ingredients：
Sn：0.35-0.50, Nb：0.45-0.55, Fe：0.24-0.36, Mo：0.04-0.12, O：0.09-0.18, surplus is Zr
And other impurity.
5. a kind of compressed water reactor nuclear power station-service zircaloy according to claim 1, it is characterised in that percentage composition by weight
Meter, is made up of following ingredients：
Sn：0.60-0.80, Nb：0.20-0.40, Fe：0.20-0.45, Mo：0.02-0.15, O：0.09-0.18, surplus is Zr
And other impurity.
6. a kind of compressed water reactor nuclear power station-service zircaloy according to claim 1, it is characterised in that percentage composition by weight
Meter, is made up of following ingredients：
Sn：0.60-0.80, Nb：0.20-0.40, Fe：0.25-0.37, Mo：0.02-0.12, Cu：0.02-0.08, O：0.09-
0.18, surplus is Zr and other impurity.
7. a kind of compressed water reactor nuclear power station-service zircaloy according to claim 6, it is characterised in that percentage composition by weight
Meter, is made up of following ingredients：
Sn：0.60-0.75, Nb：0.25-0.35, Fe：0.25-0.37, Mo：0.02-0.12, Cu：0.02-0.08, O：0.09-
0.18, surplus is Zr and other impurity.
8. a kind of compressed water reactor nuclear power station-service zircaloy according to claim 1, it is characterised in that percentage composition by weight
Meter, is made up of following ingredients：
Sn：0.60-0.80, Nb：0.25-0.35, Fe：0.25-0.37, Mo：0.02-0.12, Cu：0.02-0.08, O：0.09-
0.15, surplus is Zr and other impurity.
9. a kind of preparation method of compressed water reactor nuclear power station-service zircaloy, it is characterised in that including：
(1) dispensing is carried out according to the proportioning described in any one of claim 1~8；
(2) melting is carried out in vacuum consumable electrode arc furnace, alloy cast ingot is made；
(3) alloy cast ingot is forged into the blank material of required shape in β phase regions；
(4) by blank material in β phase region homogeneous heatings, and Quenching Treatment is carried out；
(5) blank material after quenching is subjected to hot-working in alpha phase zone；
(6) blank material after hot-working is subjected to cold working, and carries out intermediate annealing；
(7) stress relief annealing or recrystallization annealing processing are carried out, the Zirconium alloy material is obtained.
10. a kind of preparation method of compressed water reactor nuclear power station-service zircaloy according to claim 9, it is characterised in that
The forging temperature of β phase regions is the heating-up temperature of β phase regions in 900 DEG C~1200 DEG C, the step (4) in the step (3)
For 1000 DEG C~1200 DEG C, the hot processing temperature of alpha phase zone is 600 DEG C~700 DEG C in the step (5), in the step (6) in
Between the temperature annealed be that the treatment temperature of stress relief annealing or recrystallization annealing in 560 DEG C~650 DEG C, the step (7) is
480 DEG C~620 DEG C.
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106929706A (en) * | 2017-04-26 | 2017-07-07 | 上海核工程研究设计院 | A kind of zirconium-base alloy in the hot environment for nuclear reactor |
| CN112458337A (en) * | 2020-04-13 | 2021-03-09 | 国核锆铪理化检测有限公司 | Zirconium alloy, preparation method of zirconium alloy and zirconium alloy section |
| CN112458338A (en) * | 2020-04-13 | 2021-03-09 | 国核锆铪理化检测有限公司 | Zirconium alloy, preparation method of zirconium alloy and zirconium alloy section |
| CN113564419A (en) * | 2021-07-28 | 2021-10-29 | 燕山大学 | Zirconium alloy and preparation method thereof |
| CN115725875A (en) * | 2022-11-18 | 2023-03-03 | 上海交通大学 | Low-melting-point Zr-2.5Nb alloy material and alloy product |
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2017
- 2017-05-25 CN CN201710388915.8A patent/CN106957971A/en active Pending
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN106929706A (en) * | 2017-04-26 | 2017-07-07 | 上海核工程研究设计院 | A kind of zirconium-base alloy in the hot environment for nuclear reactor |
| CN112458337A (en) * | 2020-04-13 | 2021-03-09 | 国核锆铪理化检测有限公司 | Zirconium alloy, preparation method of zirconium alloy and zirconium alloy section |
| CN112458338A (en) * | 2020-04-13 | 2021-03-09 | 国核锆铪理化检测有限公司 | Zirconium alloy, preparation method of zirconium alloy and zirconium alloy section |
| CN112458338B (en) * | 2020-04-13 | 2021-09-14 | 国核宝钛锆业股份公司 | Zirconium alloy, preparation method of zirconium alloy and zirconium alloy section |
| CN112458337B (en) * | 2020-04-13 | 2022-02-18 | 国核宝钛锆业股份公司 | Zirconium alloy and preparation method of zirconium alloy profile |
| CN113564419A (en) * | 2021-07-28 | 2021-10-29 | 燕山大学 | Zirconium alloy and preparation method thereof |
| CN115725875A (en) * | 2022-11-18 | 2023-03-03 | 上海交通大学 | Low-melting-point Zr-2.5Nb alloy material and alloy product |
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