CN103898362B - A kind of water cooled nuclear reactor zirconium-base alloy - Google Patents
A kind of water cooled nuclear reactor zirconium-base alloy Download PDFInfo
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
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Abstract
The invention belongs to specialty alloy materials technical field, be specifically related to a kind of water cooled nuclear reactor zirconium-base alloy.Weight percentage, it is made up of following ingredients: Sn:0.20 0.60, Nb:0.10 0.30, at least one in 0.20 and V:0.10 0.40 two kind of element of Fe:0.30 0.60, Cr:0.05, Si or S:0.002 0.03, O:0.06 0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium.The present invention on the basis of Zr Sn Nb alloy, with the addition of other for the composition improving alloy property, and have selected suitable constituent content, the alloy property that the present invention provides meets the requirement to core structural material of the water cooled nuclear reactor high burnup.The pipe plate product prepared by this prototype alloy improves in the out-pile pure water particularly general corrosion resistance performance in lithium hydroxide aqueous solution.By the testing inspection in detailed description of the invention as a result, it is possible to think that these alloys use in reactor and have more excellent general corrosion resistance performance, higher creep resistant and fatigue properties, Flouride-resistani acid phesphatase growth performance.
Description
Technical field
The invention belongs to specialty alloy materials technical field, be specifically related to a kind of water cooled nuclear reactor zirconio and close
Gold.
Background technology
Zircaloy owing to having the advantages such as low, the excellent corrosion resistance in neutron absorption cross-section and mechanical property and
It is widely used as power producer can and other in-pile components.Development at pressurized water reactor
During, fuel design is to reactor core structure parts, such as can, screen work, guide pipe etc.,
Proposing the highest requirement, in early days, these parts are generally made up of Zr-4 alloy.The design of high fuel burn-up,
Require extend these parts time of staying in heap and improve coolant temperature, so that zircaloy parts
Being faced with more stringent corrosive environment, these high requests promote the decay resistance improving Zr-4 alloy
Research, has promoted the exploitation to the novel zirconium alloy with more excellent decay resistance.
The high request proposed fuel can for Nuclear Power Technology development, expands novel zirconium alloy in the world
Research.As in the tenth zircaloy international symposium, GEORGE P.SABOL reports " ZIRLO
In-pile corrosion behavior with Zr-4 alloy " (" In-Reactor Corrosion Performance of ZIRLO and
Zircaloy-4”,Zirconium in the Nuclear Industry:Tenth International Symposium,
ASTM STP 1245, A.M.Garde and E.R.Bradley, Eds., American Society for Testing
And Materials, Philadelphia, 1994, pp.724-744), illustrate ZIRLO and have than Zircaloy-4
Preferably decay resistance in heap.Muscovite Nikulina, A.V. in the 11st zircaloy international symposium
Report " as VVER and RBMK reactor fuel rod involucrum and the E635 zircaloy of component materials "
(" Zirconium Alloy E635as a Material for Fuel Rod Cladding and Other
Components of VVER and RBMK Cores”,Zirconium in the Nuclear Industry:
Eleventh International Symposium,ASTM STP 1295,E.R.Bradley and G.P.Sabol,
Eds., American Society for Testing and Materials, Philadelphia, 1996, pp.785-804),
The composition disclosing E635 is Zr-1.0～1.4wt%Nb-0.9～1.1wt%Sn-0.3～0.5wt%Fe, this conjunction
The out-of-pile performances of gold is better than Zircaloy-4 and E110 alloy.Method in the 12nd zircaloy international symposium
The Jean-Paul Mardon of state reports " composition and the manufacturing process impact on M5 alloy Cladding materials "
(" Influence of Composition and Fabrication Process on Out-of-Pile and In-Pile
Properties of M5 Alloy, Zirconium in the Nuclear Industry:Twelfth International
Symposium, ASTM STP 1354, Sabol, G, P, Moan, G.D., Eds., American Society for
Testing and Materials, West Conshohocken, 2000, pp.505 ~ 524), disclose under high burnup
(＞ 65GWd) decay resistance is better than the M5 alloy (Zr-1Nb-O) of Zircaloy-4.At the 16th
In zircaloy international symposium, the A.M.Garde of the U.S. reports " presurized water reactor Advanced Zirconium Alloys "
(" Advanced Zirconium Alloy for PWR Application, Zirconium in the Nuclear
Industry:sixteenth International Symposium, ASTM STP1529,2010, pp.784 ~ 826),
Disclose Cladding materials and be better than the X5A alloy of ZIRLO alloy
(Zr-0.5Sn-0.3Nb-0.35Fe-0.25Cr).
There are some researches show, in existing zircaloy, the proportioning of composition might not be in optimized scope, as incited somebody to action
After Sn content in ZIRLO alloy reduces, its decay resistance improve further (Yueh, H.K.,
Kesterson,R.L.,Comstock,R.J.,et al.,Improved ZIRLOTM cladding performance
through chemistry and process modifications.Zirconium in the Nuclear Industry:
Fourteenth International Symposium, ASTM STP1467,2004, pp.330-346.)；?
Zr-Nb alloy adds the Cu(0.05wt% of trace) the HANA-6 alloy that formed afterwards also has the most excellent
Good decay resistance (Park J.Y., Choi, B.K., Yoo, S.J.Jeong Y.H., Corrosion behavior
and oxide properties of Zr–1.1wt% Nb–0.05wt% Cu alloy,J.Nucl.Mater.,359
(2006) 59 68.)；M5 alloy in heap, running occurs in that fuel rod or fuel assembly bending and
The abnormal phenomenas 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 component
Sn and Fe, greatly improves the mechanical property of alloy, especially on the basis of keeping alloy excellent corrosion resistance
It is creep and irradiation growth performance.Therefore, on the basis of existing zircaloy optimized alloy composition proportion or
Add other alloying element and also can develop the zircaloy that decay resistance is more excellent, continuous to meet burnup
The needs improved.
The main homogeneous corrosion problem considering zircaloy in presurized water reactor, it is generally recognized that at 360 DEG C of aqueous solutions of out-pile
Qualified with zircaloy corrosion experimental examination in 400 DEG C of steam can be used for presurized water reactor, at 360 DEG C of water Han lithium of out-pile
Qualified being then more suitable in presurized water reactor height lithium concentration operating mode of experimental examination in solution.
Summary of the invention
The technical problem to be solved in the present invention be to provide a kind of novelty, there is good corrosion resistance for
The zirconium-base alloy of water cooled nuclear reactor core structural material.
In order to realize this purpose, the present invention adopts the technical scheme that:
A kind of water cooled nuclear reactor zirconium-base alloy, weight percentage, it is made up of following ingredients: Sn:
0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, Cr:0.05-0.20 or V:0.10-0.40 two kinds
At least one in element, O:0.06-0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, Cr:0.05-0.20, O:
0.06-0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, V:0.10-0.40, O:
0.06-0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, Cr:0.05-0.20 and V:
At least one in two kinds of elements of 0.10-0.40, Si or S:0.002-0.03, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.40-0.60, Nb:0.10-0.30, Fe:0.35-0.50, Cr:0.05-0.20 and V:
At least one in two kinds of elements of 0.10-0.40, Si or S:0.002-0.03, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium and impurity.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.40-0.60, Nb:0.20-0.30, Fe:0.35-0.50, Cr:0.10-0.20 and V:
At least one in two kinds of elements of 0.10-0.30, Si or S:0.002-0.03, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium and impurity.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.40-0.60, Nb:0.20-0.30, Fe:0.35-0.55, Cr:0.10-0.20 and V:
At least one in two kinds of elements of 0.10-0.30, Si or S:0.005-0.02, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium and impurity.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: in two kinds of elements of Sn:0.50, Nb:0.25, Fe:0.50, Cr:0.25 and V:0.25
At least one, Si or S:0.002, O:0.10, C: less than 0.008, N: less than 0.006, surplus is
Zirconium and impurity.
The preparation method of a kind of water cooled nuclear reactor zirconium-base alloy as above, comprises the following steps:
(1) the various components in zircaloy are carried out dispensing according to the formula ratio of alloy compositions；
(2) in vacuum consumable electrode arc furnace, carry out melting, make alloy cast ingot；
(3) alloy cast ingot is forged at the β phase region of 900 ° of C-1050 ° of C the base material of required form；
(4) by base material in the β phase region homogeneous heating of 1000 ° of C-1100 ° of C, and Quenching Treatment is carried out；
(5) the base material after quenching is carried out hot-working in the alpha phase zone of 600 ° of C-700 ° of C；
(6) the base material after hot-working is carried out cold working, and carry out intermediate annealing at 560 ° of C-650 ° of C；
(7) in 480 ° of C-620 ° of C, carry out stress relief annealing or recrystallization annealing processes, obtain described
Zirconium alloy material.
The present invention on the basis of Zr-Sn-Nb alloy, with the addition of other for the composition improving alloy property, and
Have selected suitable constituent content, the alloy property that the present invention provides meets water cooled nuclear reactor high burnup to heap
The requirement of cored structure material.The pipe plate product prepared by this prototype alloy improves at out-pile pure water special
It it is the general corrosion resistance performance in lithium hydroxide aqueous solution.Tied by the testing inspection in detailed description of the invention
Really, it is believed that these alloys use in reactor has more excellent general corrosion resistance performance, higher
Creep resistant and fatigue properties, Flouride-resistani acid phesphatase growth performance.
The material prepared of processing technique that the present invention provides is by the α-Zr crystal grain of isometry and equally distributed tiny by the
The microstructure of Secondary phase particle composition, can guarantee that have excellent use in reactor core harsh environment
Performance.
Detailed description of the invention
Below by detailed description of the invention, the present invention is described in more detail.
To from the point of view of the Zirconium alloy material of nuclear reactor, the decay resistance of alloy is the factor of overriding concern,
Production cost and machinability select to consider during alloying element on this basis, accordingly, it would be desirable in detail
Study each alloying element to the impact of corrosion resistance, mechanical performance and creep behaviour and alloy system and every kind
The amount ranges of alloying element.Zirconium-base alloy of the present invention, has resistance to the most even more excellent furuncle shape rotten
Erosion performance, having higher creep resistant and fatigue properties, have Flouride-resistani acid phesphatase growth performance, concrete condition is as follows:
(1) zirconium (Zr)
By the consideration to neutron absorption factor, the present invention selects zirconium as basic element, is also contemplated for adding simultaneously
It is added to the neutron-absorbing situation of other alloying elements in basic zirconium.
(2) stannum (Sn)
Stannum can the α-phase of stabilised zirconia, its intensity can be increased, and the nitrogen illeffects to corrosion can be offset.When
When stannum consumption is few, it is impossible to reach required effect.In the present invention, Sn interpolation content is in 0.20-0.60 weight %,
It ensure that alloy has excellent decay resistance and good mechanical property.
(3) niobium (Nb)
Niobium can the β-phase of stabilised zirconia, niobium has higher invigoration effect to zirconium.It is quick that niobium consumption crosses multipair heat treatment
Sense.In the present invention, Nb interpolation content is in 0.10-0.30 weight %, and it ensure that alloy is at pure water and hydrogen-oxygen
Change in lithium aqueous solution and there is excellent decay resistance and good mechanical property.
(4) ferrum (Fe)
Ferrum can improve alloy corrosion resistance and mechanical property, but the consumption of ferrum too much or very few all can have unfavorable
Impact.The content that in the present invention, Fe adds in 0.30-0.60 weight %, its ensure that alloy at pure water and
Lithium hydroxide aqueous solution has excellent decay resistance.
(5) chromium (Cr)
Chromium can improve alloy corrosion resistance and mechanical property, but consumption too much has adverse influence.This
The chromium content of bright middle interpolation controls in 0.05-0.2 weight %, and it ensure that alloy is at pure water and Lithium hydrate water
Solution has excellent decay resistance and good mechanical property.
(6) vanadium (V)
Vanadium can improve alloy corrosion resistance and mechanical property, but consumption too much has adverse influence.This
The content of vanadium of bright middle interpolation controls in 0.1-0.4 weight %, and it ensure that alloy is at pure water and Lithium hydrate water
Solution has excellent decay resistance and good mechanical property.
(7) silicon (Si)
Silicon can affect being uniformly distributed of alloy precipitated phase, thus the consumption of silicon too much has adverse influence.
In the present invention, the silicone content added being less than 0.03 weight %, it ensure that alloy is at lithium hydroxide aqueous solution
In there is excellent decay resistance.
(8) sulfur (S)
Add appropriate S in the alloy and can improve alloy creep intensity, simultaneously improve the corrosion resistance of alloy.
But the consumption of sulfur too much has adverse influence.The sulfur content added is less than 0.03 weight % by the present invention,
It ensure that have excellent decay resistance in alloy high-temp steam.
(9) oxygen (O)
Oxygen can the α-phase of stabilised zirconia, alloy adds oxygen and can improve yield strength.In the present invention, oxygen adds
Content is in 0.06-0.15 weight %, and it ensure that alloy has enough mechanical performances and creep-resistant property.
The increase of oxygen content, greatly reduces the control difficulty in material processing.
(10) carbon (C)
When carbon in alloy exists as inevitable impurity element and content is higher, can drop low-alloyed anti-
Corrosive nature.In the present invention, the percentage by weight of C is less than 0.008%, its ensure that alloy at high-temperature water and
Steam has excellent decay resistance.
(11) nitrogen (N)
When nitrogen in alloy exists as inevitable impurity element and content is higher, can drop low-alloyed anti-
Corrosive nature.In the present invention, the percentage by weight of N is less than 0.006%, its ensure that alloy at high-temperature water and
Steam has excellent decay resistance.
Concrete, the technical scheme is that
A kind of water cooled nuclear reactor zirconium-base alloy, weight percentage, it is made up of following ingredients: Sn:
0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, Cr:0.05-0.20 or V:0.10-0.40 two kinds
At least one in element, O:0.06-0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, Cr:0.05-0.20, O:
0.06-0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, V:0.10-0.40, O:
0.06-0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.20-0.60, Nb:0.10-0.30, Fe:0.30-0.60, Cr:0.05-0.20 and V:
At least one in two kinds of elements of 0.10-0.40, Si or S:0.002-0.03, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.40-0.60, Nb:0.10-0.30, Fe:0.35-0.50, Cr:0.05-0.20 and V:
At least one in two kinds of elements of 0.10-0.40, Si or S:0.002-0.03, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium and impurity.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.40-0.60, Nb:0.20-0.30, Fe:0.35-0.50, Cr:0.10-0.20 and V:
At least one in two kinds of elements of 0.10-0.30, Si or S:0.002-0.03, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium and impurity.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.40-0.60, Nb:0.20-0.30, Fe:0.35-0.55, Cr:0.10-0.20 and V:
At least one in two kinds of elements of 0.10-0.30, Si or S:0.005-0.02, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium and impurity.
A kind of water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: in two kinds of elements of Sn:0.50, Nb:0.25, Fe:0.50, Cr:0.25 and V:0.25
At least one, Si or S:0.002, O:0.10, C: less than 0.008, N: less than 0.006, surplus is
Zirconium and impurity.
Table 1 is the composition of alloy provided by the present invention, and in table, 14* is Zr-4 alloy composition and tests accordingly
Assay, in table 1, each content is respective components percentage by weight in the alloy.
Table 1 alloy provided by the present invention forms
The preparation method of a kind of used by nuclear reactor Zirconium alloy material as above, comprises the following steps:
(1) the various components in zircaloy are carried out dispensing according to the formula ratio of alloy compositions；
(2) in vacuum consumable electrode arc furnace, carry out melting, make alloy cast ingot；
(3) alloy cast ingot is forged at the β phase region of 900 ° of C-1050 ° of C the base material of required form；
(4) by base material in the β phase region homogeneous heating of 1000 ° of C-1100 ° of C, and Quenching Treatment is carried out；
(5) the base material after quenching is carried out hot-working in the alpha phase zone of 600 ° of C-700 ° of C；
(6) the base material after hot-working is carried out cold working, and carry out intermediate annealing at 560 ° of C-650 ° of C；
(7) in 480 ° of C-620 ° of C, carry out stress relief annealing or recrystallization annealing processes, obtain described
Zirconium alloy material.
The material prepared by above-mentioned processing technique is by the α-Zr crystal grain of isometry and equally distributed tiny second phase grain
Molecular microstructure, can guarantee that have excellent serviceability in reactor core harsh environment.
The alloy material prepared by said method, its performance test results is as shown in table 2, table 3 and table 4.Table 2
Described in experimental condition particularly as follows: etching condition is 360 ° of C, 18.6MPa deionized waters；Described in table 3
Experimental condition is: 360 ° of C, 18.6MPa containing 70 μ g/g lithium aqueous solutions (with Lithium hydrate form join from
In sub-water)；The described respectively experimental condition of table 4 and table 5 be 400 ° of C, 10.3MPa deionized water steam and
500 ° of C, 10.3MPa deionized water steam.Etching time in 360 ° of C water and 400 ° of C steam ambient divides
It is not 300 days (d), table gives the corrosion rate (mg/dm of every kind of alloy2/ d), for the ease of comparing conjunction
The relative performance of gold, and in table, give relatively corrosive speed.From table (2,3,4) it can be seen that
All of alloy is at 360 ° of C pure water, lithium hydroxide aqueous solutions, and all shows good in 400 ° of C steam
Good decay resistance.
Table 2 alloy material provided by the present invention corrode 300 days in 360 ° of C deionized waters after corrosion rate
Table 3 alloy material provided by the present invention at 360 ° of C containing the corrosion rate after corroding 300 days in lithium aqueous solution
Table 4 alloy material provided by the present invention corrode in water vapour 300 days after corrosion rate
From the data of table 2, table 3 and table 4 it can be seen that alloy of the present invention is rotten above-mentioned three kinds of corrosive mediums
Erosion performance is superior to Zr-4 alloy, meets the power station requirement to cladding materials corrosive nature.
In sum, the application example that the present invention provides shows, alloy of the present invention is at above-mentioned 3 kinds of water chemistry bars
Under part corrosion time all show the most excellent decay resistance, 360 DEG C/18.6MPa deionized water, 360 DEG C
Corrosion rate in/18.6MPa LiOH aqueous solution, 400 DEG C/10.3MPa superheated steam is substantially better than Zr-4
Alloy.
Owing to present invention employs the composition range of preferred Sn, Nb, Fe, Cr, V, Si and S etc.,
The interaction between alloying element in the range of this, in conjunction with machining at low temperature technique, creates and expects not in advance
The effect arrived, this effect is mainly manifested in two aspects: 1) alloy of the present invention is at above-mentioned 3 kinds of water chemistry bars
The most excellent decay resistance is all shown during corrosion, hence it is evident that be better than Zr-4 alloy under part.2) present invention closes
Gold through low temperature process process after obtain small and dispersed distribution the second phase, improve alloy mechanical property (as
Creep and fatigue behaviour) and Flouride-resistani acid phesphatase growth performance.
Claims (3)
1. a water cooled nuclear reactor zirconium-base alloy, it is characterised in that: weight percentage, by following
One-tenth is grouped into: Sn:0.20-0.60,0.1≤Nb ＜ 0.2, Fe:0.30-0.60, Cr:0.05-0.20 and V:
At least one in two kinds of elements of 0.10-0.40, Si or S:0.013-0.03, O:0.06-0.15, C: be less than
0.008, N: less than 0.006, surplus is zirconium and impurity.
2. a kind of water cooled nuclear reactor zirconium-base alloy as claimed in claim 1, it is characterised in that: by weight
Amount percentage composition meter, is made up of following ingredients: Sn:0.40-0.60,0.1≤Nb ＜ 0.2, Fe:0.35-0.50,
At least one in two kinds of elements of Cr:0.05-0.20 and V:0.10-0.40, Si or S:0.013-0.03, O:
0.06-0.15, C: less than 0.008, N: less than 0.006, surplus is zirconium and impurity.
3. a kind of water cooled nuclear reactor zirconium-base alloy as described in claim any one of claim 1,2
Preparation method, it is characterised in that comprise the following steps:
(1) the various components in zircaloy are carried out dispensing according to the formula ratio of alloy compositions；
(2) in vacuum consumable electrode arc furnace, carry out melting, make alloy cast ingot；
(3) alloy cast ingot is forged at the β phase region of 900 DEG C-1050 DEG C the base material of required form；
(4) by base material the β phase region homogeneous heating of 1000 DEG C-1080 DEG C, and Quenching Treatment is carried out；
(5) the base material after quenching is carried out hot-working the alpha phase zone of 600 DEG C-700 DEG C；
(6) the base material after hot-working is carried out cold working, and carry out intermediate annealing at 560 DEG C-650 DEG C；
(7) in 480 DEG C-620 DEG C, carry out stress relief annealing or recrystallization annealing processes, obtain described
Zirconium alloy material.
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| CN105543560B (en) * | 2016-01-06 | 2018-09-11 | 中国核动力研究设计院 | A kind of nuclear-used zirconium alloy |
| CN107304465A (en) * | 2016-04-19 | 2017-10-31 | 中国核动力研究设计院 | A kind of PWR fuel assembly zircaloy |
| 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 |
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