CN107304465A - A kind of PWR fuel assembly zircaloy - Google Patents
A kind of PWR fuel assembly zircaloy Download PDFInfo
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- CN107304465A CN107304465A CN201610246460.1A CN201610246460A CN107304465A CN 107304465 A CN107304465 A CN 107304465A CN 201610246460 A CN201610246460 A CN 201610246460A CN 107304465 A CN107304465 A CN 107304465A
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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
- C22C—ALLOYS
- C22C1/00—Making non-ferrous alloys
- C22C1/02—Making non-ferrous alloys by melting
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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
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- Engineering & Computer Science (AREA)
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- Mechanical Engineering (AREA)
- Metallurgy (AREA)
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- Thermal Sciences (AREA)
- Crystallography & Structural Chemistry (AREA)
- Turbine Rotor Nozzle Sealing (AREA)
Abstract
The invention discloses a kind of PWR fuel assembly zircaloy, weight percentage is made up of following ingredients：Sn：0.2 0.6%, Nb：0.1 0.5%, Fe：0.61 0.85%, Cr or V：0.1 0.3%, Ce or Sb：0.001 0.1%, O：0.09 0.13%, C：Less than 0.008%, N：Less than 0.006%, surplus is Zr.The present invention to the composition in zircaloy by optimizing and the content of constituent being made adjustment, to improve the corrosive nature of alloy, the alloy property that the present invention is provided is met requirement of the power producer high burnup to core structural material.The product prepared by this prototype alloy improves the general corrosion resistance performance in out-pile pure water and lithium hydroxide aqueous solution, improves the resistance to Nodular Corrosion in high-temperature steam.
Description
Technical field
The invention belongs to specialty alloy materials technical field, and in particular to a kind of PWR fuel assembly is closed with zirconium
Gold.
Background technology
Zircaloy is small due to thermal neutron absorption cross section, while there is good anti-corruption in high-temperature high pressure water and steam
Corrosion energy, there is fairly good anti-neutron irradiation performance in heap, thus is commonly used as the reaction of nuclear power water cooling
The cladding materials of heap, is also the cladding materials that current nuclear power plant reactor is uniquely used.In light-water reactor
In evolution, fuel design is to reactor core structure part, such as can, screen work, guiding
Pipe etc., it is proposed that very high requirement.In early days, cladding materials is generally made up of Zr-4 alloys, afterwards high fuel
The design requirement of burnup improves the residence time of coolant temperature and extension zirconium alloy cladding in heap, so that
Obtain zirconium alloy cladding and be faced with more stringent corrosive environment, it is resistance to that these high requests promote improvement Zr-4 alloys
The research of corrosive nature, while also having promoted the exploitation to the novel zirconium alloy with more excellent corrosion resistance.
With the further development of nuclear power, it is necessary to which to improve core anti-on the basis of reactor safety is ensured
Answer heap economy, reduction nuclear power operating cost, thus fuel assembly is proposed the long-lived phase, high burnup,
Zero damaged target.This means the water side corrosion of zirconium alloy cladding is aggravated, hydrogen-sucking amount increases, exposure time
Growth, pellet and cladding interaction increase and internal pressure rise etc., so that the performance to zircaloy is proposed
Higher requirement.Develop the high request proposed to fuel can for Nuclear Power Technology, expand in the world
The research of novel zirconium alloy, obtain the ZIRLO that there is more preferable decay resistance than Zr-4 alloy, E635,
The novel zirconium alloys such as M5, X5A.There are some researches show the proportioning of composition might not be in existing zircaloy
In optimized scope, such as by after the Sn contents reduction in ZIRLO alloys, its decay resistance is further improved；
The HANA-6 alloys that micro Cu (0.05wt%) formed afterwards are added in Zr-Nb alloys also to be had very
Excellent decay resistance；M5 alloys occurred in that in heap in running fuel rod or fuel assembly bending with
And the anomaly such as Flouride-resistani acid phesphatase growth performance difference, therefore, France with the addition of a small amount of on the basis of M5 alloying components
Sn and Fe, the mechanical property of alloy is greatly improved on the basis of alloy excellent corrosion resistance is kept, especially
It is creep and irradiation growth performance.Therefore, on the basis of existing zircaloy optimized alloy composition proportion or
Person, which adds other alloying elements, can also develop the more excellent zircaloy of decay resistance, to meet burnup not
The need for disconnected raising.
In addition, after alloying component determination, conjunction can also be further improved using suitable heat processing technique
The decay resistance of gold.Such as in the higher zircaloy of Nb contents, including ZIRLO, M5 and N36 etc.,
After hot worked temperature is improved, satiated in the roughening and uneven distribution and alloy substrate due to the second phase
With solid solution Nb, decay resistance can be caused to be deteriorated, thus all emphasize to use " low temperature process technique ", that is, adopted
The second phase group of small and dispersed is resulted in the low temperature process technique of relatively low hot processing temperature and annealing temperature
Knit, so as to greatly improve the decay resistance and mechanical property of alloy.
The content of the invention
The present invention is by the composition in existing zircaloy and with further optimization is compared to, to obtain a kind of novelty
, novel zirconium alloy with good corrosion resistance.
In order to realize this purpose, the present invention is adopted the technical scheme that：
A kind of PWR fuel assembly zircaloy, weight percentage is made up of following ingredients：
Sn：0.2-0.6%, Nb：0.1-0.5%, Fe：0.61-0.85%, Cr or V：0.1-0.3%, Ce or Sb：
0.001-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：Less than 0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.4%, Nb：0.1-0.5%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.4-0.6%, Nb：0.1-0.5%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.6%, Nb：0.1-0.3%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.4%, Nb：0.1-0.3%, Fe：0.61-0.8%, Cr or V：
0.1-0.3%, Ce or Sb：0.05-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.6%, Nb：0.3-0.5%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.22%, Nb：0.1%, Fe：0.64%, Cr or V：0.15%,
Ce or Sb：0.05%, O：0.11%, C：0.006%, N：0.005%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.48%, Nb：0.12%, Fe：0.7%, Cr or V：0.2%,
Ce or Sb：0.04%, O：0.09%, C：0.005%, N：0.004%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.52%, Nb：0.18%, Fe：0.71%, Cr or V：0.26%,
O：0.1%, C：0.007%, N：0.004%, surplus is Zr.
The present invention using Zr-Sn-Nb alloy systems as base, added in the alloy system other alloying element Fe,
Cr or V, alternative addition Ce or Sb, interacts by using alloying element, rationally designs alloy
Elemental composition is matched, and can be produced unexpected effect to alloy decay resistance, can largely be improved
The out-pile corrosion resistance of alloy, it is contemplated that there is alloy excellent corrosion resistance and Flouride-resistani acid phesphatase to give birth in heap
Long, croop property.
A kind of preparation method of nuclear-used zirconium alloy as described above comprises the following steps：
(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) by the blank material of alloy cast ingot shape needed for 900 DEG C -1050 DEG C of β phase regions are forged into；
(4) the β phase region homogeneous heatings by blank material at 1000 DEG C -1100 DEG C, and carry out Quenching Treatment；
(5) the β phase regions by the blank material after quenching at 600 DEG C -700 DEG C carry out hot-working；
(6) blank material after hot-working is subjected to cold working, and in 560 DEG C of -650 DEG C of progress intermediate annealings；
(7) stress relief annealing or recrystallization annealing processing are carried out in 480 DEG C -620 DEG C, the zirconium is obtained
Alloy material.
To sum up, the beneficial effects of the invention are as follows：The present invention with the addition of other on the basis of Zr-Sn-Nb alloys
Elemental composition for improving alloy property, selects appropriate constituent content, and control solid solution, phase component,
Second phase crystal structure, composition and species, to improve the corrosive nature of alloy, the alloy that the present invention is provided
Performance meets requirement of the power producer high burnup to core structural material.Prepared by this prototype alloy
Product improves the general corrosion resistance performance in out-pile pure water and lithium hydroxide aqueous solution, improves in high temperature
Resistance to Nodular Corrosion in steam.Pass through the testing inspection result in embodiment, it is believed that this
A little alloys used in reactor with more excellent resistance to uniform Nodular Corrosion, higher creep resistant and
Fatigue properties, Flouride-resistani acid phesphatase growth performance.
Embodiment
With reference to embodiment, the present invention is described in further detail, but embodiments of the present invention are not
It is limited to this.
For the zircaloy for nuclear reactor cladding materials, the decay resistance of zircaloy is overriding concern
Factor, on this basis production cost and machinability be selection alloying element when need consider.Therefore,
Need to study influence and alloy of each alloying element to corrosion resistance, mechanical performance and creep behaviour in detail
The amount ranges of every kind of alloying element in system.Zircaloy of the present invention has more excellent resistance to uniform
Nodular Corrosion, with higher creep resistant and fatigue properties, Flouride-resistani acid phesphatase growth performance.
Each alloys producing and consumption concrete condition is as follows：
(1) zirconium (Zr)
In view of the consideration to neutron economy, the zirconium of present invention selection neutron absorption cross-section smaller (0.185b) is made
For matrix element, while being also contemplated for being added to the neutron absorption cross-section situation of other alloying elements in zirconium base body.
(2) tin (Sn)
Tin is capable of the α phases of stabilised zirconia, increases its intensity, and can offset illeffects of the nitrogen to corrosion.Work as tin
When consumption is very few, it is impossible to reach required effect.Sn adds content in 0.2-0.6% (weight hundred in the present invention
Divide ratio), it ensure that alloy has excellent decay resistance and good mechanical property.
(3) niobium (Nb)
Niobium is capable of the β phases of stabilised zirconia, there is higher invigoration effect to zirconium.When niobium consumption is excessive, at heat
Reason is sensitive.Nb adds content at 0.1-0.5% (percentage by weight) in the present invention, ensure that alloy has
Excellent decay resistance and good mechanical property.
(4) iron (Fe)
Iron can improve alloy corrosion resistance and mechanical property, but iron consumption it is excessive or it is very few can all produce it is unfavorable
Influence.The content that Fe is added in the present invention ensure that alloy at 0.61-0.85% (percentage by weight)
With excellent decay resistance.
(5) chromium (Cr)
Chromium can improve alloy corrosion resistance and mechanical property, but chromium consumption it is excessive or it is very few can all produce it is unfavorable
Influence.The content that Cr is added in the present invention ensure that alloy has at 0.1-0.3% (percentage by weight)
There is excellent decay resistance.
(6) vanadium (V)
Alum can improve alloy corrosion resistance and mechanical property, and the corrosive nature of aluminiferous zircaloy compares heat treatment
It is more sensitive.The content that V is added in the present invention ensure that alloy has at 0.1-0.3% (percentage by weight)
Excellent decay resistance.
(7) cerium (Ce)
Cerium can improve alloy corrosion resistance energy, but cerium consumption it is excessive when easily form the phase of bulky grain second.Hair
The content of bright middle Ce addition is less than 0.1% (percentage by weight), ensure that alloy has excellent corrosion-resistant
Performance.
(8) antimony (Sb)
Antimony can improve alloy corrosion resistance energy, but antimony consumption it is excessive when easily form the phase of bulky grain second.Hair
The content of bright middle Sb addition is less than 0.1% (percentage by weight), ensure that alloy has excellent corrosion-resistant
Performance.
(9) oxygen (O)
Oxygen, which is capable of addition oxygen in the α phases of stabilised zirconia, alloy, can improve yield strength.O is added in the present invention
Content ensure that alloy has enough mechanical performances and creep resistant at 0.09-0.13% (percentage by weight)
Performance.The increase of oxygen content, greatly reduces the control difficulty in material processing.
(10) carbon (C)
Carbon in alloy exists as inevitable impurity element, and content it is higher when, alloy can be reduced
Corrosion resistance.C percentage by weight is less than 0.008% in the present invention, ensure that alloy has excellent
Decay resistance.
(11) nitrogen (N)
Nitrogen in alloy exists as inevitable impurity element, and content it is higher when, alloy can be reduced
Corrosion resistance.N percentage by weight is less than 0.006% in the present invention, ensure that alloy has excellent
Decay resistance.
A kind of PWR fuel assembly zircaloy of the present invention, weight percentage, by following ingredients group
Into：Sn：0.2-0.6%, Nb：0.1-0.5%, Fe：0.61-0.85%, Cr or V：0.1-0.3%, Ce or
Sb：0.001-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：Less than 0.006%, surplus is
Zr。
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.4%, Nb：0.1-0.5%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.4-0.6%, Nb：0.1-0.5%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.6%, Nb：0.1-0.3%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.4%, Nb：0.1-0.3%, Fe：0.61-0.8%, Cr or V：
0.1-0.3%, Ce or Sb：0.05-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.2-0.6%, Nb：0.3-0.5%, Fe：0.61-0.85%, Cr or
V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.22%, Nb：0.1%, Fe：0.64%, Cr or V：0.15%,
Ce or Sb：0.05%, O：0.11%, C：0.006%, N：0.005%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.48%, Nb：0.12%, Fe：0.7%, Cr or V：0.2%,
Ce or Sb：0.04%, O：0.09%, C：0.005%, N：0.004%, surplus is Zr.
Further, a kind of PWR fuel assembly zircaloy as described above, by weight percentage composition
Meter, is made up of following ingredients：Sn：0.52%, Nb：0.18%, Fe：0.71%, Cr or V：0.26%,
O：0.1%, C：0.007%, N：0.004%, surplus is Zr.
Table 1 is the constituent (percentage by weight) of alloy provided by the present invention, and 9* and 10* is respectively in table
The surplus of each alloy provided in the constituent of Zr-4 alloys and N36 alloys, table 1 is Zr and other are miscellaneous
Matter.
The constituent of the alloy provided by the present invention of table 1
The alloy provided in upper table 1 is prepared in accordance with the following methods：
(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) by the blank material of alloy cast ingot shape needed for 900 DEG C -1050 DEG C of β phase regions are forged into；
(4) the β phase region homogeneous heatings by blank material at 1000 DEG C -1100 DEG C, and carry out Quenching Treatment；
(5) the β phase regions by the blank material after quenching at 600 DEG C -700 DEG C carry out hot-working；
(6) blank material after hot-working is subjected to cold working, and in 560 DEG C of -650 DEG C of progress intermediate annealings；
(7) stress relief annealing or recrystallization annealing processing are carried out in 480 DEG C -620 DEG C, the zirconium is obtained
Alloy material.
The Zirconium alloy material prepared by above-mentioned processing technology has equiaxial α-Zr crystal grain and equally distributed tiny
The microstructure of second phase particles composition, can guarantee that has excellent make in reactor core harsh environment
Use performance.The Zirconium alloy material prepared by the above method, its out-pile corrosive nature testing result such as institute of table 2
Show, alloy material respectively provided by the present invention corrode 300 days in 360 DEG C of pure water after corrosion rate,
In 360 DEG C of water containing lithium corrode 300 days after corrosion rate and in 400 DEG C of steam corrode 300 days after corruption
Lose speed.
The corrosive nature of the alloy provided by the present invention of table 2
From Table 2, it can be seen that alloy material provided by the present invention 360 DEG C of pure water, the aqueous solution containing lithium with
And show good decay resistance in 400 DEG C of steam.
In summary, the application example that the present invention is provided shows that alloy of the present invention is in above-mentioned 3 kinds of water chemistry bars
Good decay resistance is all shown when corroding under part, alloy is in 360 DEG C/18.6MPa pure water and 400 DEG C
Corrosion rate in/10.3MPa steam is significantly lower than Zr-4 and N36 alloys, in 360 DEG C/18.6MPa LiOH
Corrosion rate in the aqueous solution is less than Zr-4 alloys, is less than or is close with N36 alloys.
Due to present invention employs preferred Sn, Nb, Fe, Cr or V composition range, optionally
Ce or Sb is added, by using the interaction between alloying element, with reference to low temperature process technique, is generated
Effect unexpected in advance, this effect is mainly manifested in two aspects：1) alloy of the present invention is above-mentioned 3
Good decay resistance is all shown when corroding under the conditions of kind water chemistry, hence it is evident that better than Zr-4 alloys, be better than
Or it is not less than N36 zircaloys；2) alloy of the present invention obtains small and dispersed distribution after being processed through low temperature process
Second phase, improves the mechanical property (such as creep and fatigue behaviour) and Flouride-resistani acid phesphatase growth performance of alloy.
As described above, the present invention can be realized preferably.It is described above, be only presently preferred embodiments of the present invention and
, any formal limitation not is made to the present invention, according to the technical spirit of the present invention, the present invention's
Within spirit and principle, any simple modification, equivalent substitution and improvement for being made to above example etc.,
Still fall within the protection domain of technical solution of the present invention.
Claims (9)
1. a kind of PWR fuel assembly zircaloy, it is characterised in that：Weight percentage, under
Row composition is constituted：Sn：0.2-0.6%, Nb：0.1-0.5%, Fe：0.61-0.85%, Cr or V：
0.1-0.3%, Ce or Sb：0.001-0.1%, O：0.09-0.13%, C：Less than 0.008%, N：It is less than
0.006%, surplus is Zr.
2. a kind of PWR fuel assembly zircaloy as claimed in claim 1, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.2-0.4%, Nb：0.1-0.5%, Fe：
0.61-0.85%, Cr or V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：It is less than
0.008%, N：Less than 0.006%, surplus is Zr.
3. a kind of PWR fuel assembly zircaloy as claimed in claim 1, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.4-0.6%, Nb：0.1-0.5%, Fe：
0.61-0.85%, Cr or V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：It is less than
0.008%, N：Less than 0.006%, surplus is Zr.
4. a kind of PWR fuel assembly zircaloy as claimed in claim 1, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.2-0.6%, Nb：0.1-0.3%, Fe：
0.61-0.85%, Cr or V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：It is less than
0.008%, N：Less than 0.006%, surplus is Zr.
5. a kind of PWR fuel assembly zircaloy as claimed in claim 4, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.2-0.4%, Nb：0.1-0.3%, Fe：
0.61-0.8%, Cr or V：0.1-0.3%, Ce or Sb：0.05-0.1%, O：0.09-0.13%, C：It is small
In 0.008%, N：Less than 0.006%, surplus is Zr.
6. a kind of PWR fuel assembly zircaloy as claimed in claim 1, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.2-0.6%, Nb：0.3-0.5%, Fe：
0.61-0.85%, Cr or V：0.1-0.3%, Ce or Sb：0-0.1%, O：0.09-0.13%, C：It is less than
0.008%, N：Less than 0.006%, surplus is Zr.
7. a kind of PWR fuel assembly zircaloy as claimed in claim 1, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.22%, Nb：0.1%, Fe：0.64%, Cr or
V：0.15%, Ce or Sb：0.05%, O：0.11%, C：0.006%, N：0.005%, surplus is
Zr。
8. a kind of PWR fuel assembly zircaloy as claimed in claim 1, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.48%, Nb：0.12%, Fe：0.7%, Cr or
V：0.2%, Ce or Sb：0.04%, O：0.09%, C：0.005%, N：0.004%, surplus is
Zr。
9. a kind of PWR fuel assembly zircaloy as claimed in claim 1, it is characterised in that：By weight
Percentage composition meter is measured, is made up of following ingredients：Sn：0.52%, Nb：0.18%, Fe：0.71%, Cr or
V：0.26%, O：0.1%, C：0.007%, N：0.004%, surplus is Zr.
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| CN201610246460.1A CN107304465A (en) | 2016-04-19 | 2016-04-19 | A kind of PWR fuel assembly zircaloy |
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Cited By (4)
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| CN110779856A (en) * | 2019-11-20 | 2020-02-11 | 中国核动力研究设计院 | Sample installation device and method for lead-bismuth alloy melt corrosion test |
| CN110904359A (en) * | 2019-12-18 | 2020-03-24 | 佛山科学技术学院 | Corrosion-resistant zirconium alloy |
| CN110964946A (en) * | 2019-12-18 | 2020-04-07 | 佛山科学技术学院 | Zirconium alloy |
| TWI752481B (en) * | 2019-04-30 | 2022-01-11 | 美商西屋電器公司 | Improved corrosion resistance of additively-manufactured zirconium alloys |
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