CN105018795B - A kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance - Google Patents
A kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance Download PDFInfo
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Abstract
The invention provides a kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance, the alloy is made up of the composition of following mass percent：Nb 0.8%~1.5%, V 0.005%~0.2%, Fe 0.005%~0.2%, O 0.07%~0.14%, surplus is Zr and inevitable impurity.Alloy of the present invention has excellent decay resistance, and the alloy is immersed in deionized water, is 360 DEG C in temperature, pressure is corrodes 200 days under conditions of 18.6MPa, the surrosion of alloy is not more than 65mgdm‑2；The alloy is placed in deionized water steam atmosphere, is 500 DEG C in temperature, pressure is corrodes 500 hours under conditions of 10.3MPa, the surrosion of alloy is not more than 300mgdm‑2。
Description
Technical field
The invention belongs to zirconium-based alloy material technical field, and in particular to a kind of nuclear reactor combustion of fine corrosion resistance
Expect involucrum zirconium-base alloy.
Background technology
Zirconium and its alloy are widely used in power producer as structure member and fuel can, and this is mainly
Because zirconium has low thermal neutron absorption cross section, there are strong corrosion resistance and high mechanical strength in high-temperature water.It is anti-in core
Answer in heap, the burnup for improving nuclear fuel is to reduce the effective way of nuclear power cost, and for presurized water reactor, further improves burnup
Key constraints are the water side corrosion of fuel can zircaloy and inhale hydrogen.Therefore, this is just carried to the corrosion resistance of zircaloy
Higher requirement is gone out.
In recent years, to meet reactor fuel assemblies long-lived phase, high burnup, zero damaged requirement, countries in the world are all to existing
Some zircaloys are improved, to improve its combination property.This effort can substantially be divided into both direction：One is changing zirconium
The composition of alloying element, ratio and processing technology in alloy；The second is carrying out surface modification treatment to existing zircaloy.This two side
The effort in face all achieves certain achievement, is effectively improved the security and economy of zircaloy.Zr- is currently mainly used
2-in-1 gold, Zr-4 alloys, M5TMAlloy, E635 alloys, ZIRLOTMAlloy etc..
According to pertinent literature, have at present general all containing a small amount of Nb, Sn, Cr, Fe etc. in the zircaloy composition of the trade mark
Metallic element.For example：Zr-2 alloys contain 1.2wt%~1.7wt%Sn, 0.07wt%~0.2wt%Fe, 0.05wt%~
0.15wt%Cr, 0.03wt%~0.08wt%Ni and 0.08wt%~0.15wt%O；Zr-4 alloys contain 1.2wt%~
1.7wt%Sn, 0.18wt%~0.24wt%Fe, 0.07wt%~0.13wt%Cr and 0.08wt%~0.15wt%O；E635
Zircaloy contains 1.2wt%~1.3wt%Sn, 0.34wt%~0.4wt%Fe and 0.95wt%~1.05wt%Nb；The U.S. is special
The zirconium-base alloy of trade name ZIRLO disclosed in sharp US4649023 contain 0.7wt%~1.5wt%Sn, 0.07wt%~
0.14wt%Fe and 0.5wt%~2.0wt%Nb；M5 zircaloys contain 0.8wt%~1.2wt%Nb and 0.09wt%~
0.15wt%O；NDA zircaloys contain 1.0wt%Sn, 0.28wt%Fe, 0.16wt%Cr, 0.01wt%Ni and 0.10wt%
Nb；" a kind of zirconium niobium containing magnesium for nuclear reactor fuel can is closed Patent No. ZL200810232542.6 Chinese patent
Gold " contains 0.8wt%~1.2wt%Nb, 0.02wt%~0.5wt%Mg and 700ppm~1400ppm O；Patent No.
A kind of ZL200810232541.1 Chinese patent " nuclear reactor zirconium-base alloy " containing 0.6wt%~1.2wt%Nb,
0.004wt%~0.15wt%Cu, 10ppm~25ppm S and 0.06wt%~0.16wt%O；Patent No.
ZL200910023972.1 " a kind of corrosion-resistant Zr-based alloy for cladding nuclear fuels " containing 0.05wt%~1.5wt%Nb,
0.01wt%~0.5wt%Sn, 0wt%~0.5wt%Bi, 0.07wt%~0.2wt%Fe, 0.05wt%~0.15wt%
Te, 5ppm~25ppm S and 0.07wt%~0.15wt%O；Patent No. ZL200910023973.6 Chinese patent is " a kind of
Niobium-containing zirconium base alloy used by nuclear fuel jacketing " containing 0.75wt%~1.3wt%Nb, 0wt%~0.3wt%Fe, 0wt%~
0.3wt%Bi, 0wt%~0.5wt%Cu, 0.01wt%~1wt%Te, 0ppm~150ppm S and 0.07wt%~
0.15wt%O；A kind of Chinese patent " the corrosion-resistant zirconium of used by nuclear fuel jacketing zirconium-tin-niobium system of Patent No. 201010137351.9
Based alloy " contains 0.6wt%~1.4wt%Sn, 0.10wt%~1.5wt%Nb, 0.1wt%~0.5wt%Fe, 0.02wt%
~0.3wt%Cr, O0.005wt%~0.5wt%Mg, O20wt%~0.5wt%Ce, 0wt%~0.5wt%Y2O3, 0wt%
~0.015wt%SiO2, 0wt%~0.03wt%V2O3With 0.07wt%~0.15wt%O.Above patent is all by addition
Alloying element improves the decay resistance of zircaloy.
In summary, the final goal that used by nuclear reactor Zirconium alloy material is pursued is the corrosion-resistant of continuous improvement zircaloy
Performance and the growth of anti-neutron irradiation, irradiation creep performance, anti-hydrogen sucking function etc..Therefore, research alloy compositions proportioning, proposes one
New alloying component is planted, zircaloy of the exploitation with more excellent corrosion resistance, is that those skilled in the art seek assiduously simultaneously
The target untiringly struggled for it.
The content of the invention
The technical problems to be solved by the invention are that there is provided a kind of decay resistance for above-mentioned the deficiencies in the prior art
Excellent nuclear reactor fuel can zirconium-base alloy.The alloy has excellent decay resistance, by the alloy immersion go from
It it is 360 DEG C in temperature, pressure is corrodes 200 days under conditions of 18.6MPa, the surrosion of alloy is not more than in sub- water
65mg·dm-2；The alloy is placed in deionized water steam atmosphere, is 500 DEG C in temperature, pressure is under conditions of 10.3MPa
Corrosion 500 hours, the surrosion of alloy is not more than 300mgdm-2。
In order to solve the above technical problems, the technical solution adopted by the present invention is：A kind of nuclear reaction of fine corrosion resistance
Heap fuel can zirconium-base alloy, it is characterised in that the alloy is made up of the composition of following mass percent：Nb 0.8%~
1.5%, V 0.005%~0.2%, Fe 0.005%~0.2%, O0.07%~0.14%, surplus is Zr and inevitable
Impurity；The alloy has excellent decay resistance, is specially：The alloy is immersed in deionized water, is 360 DEG C in temperature,
Pressure is corrodes 200 days under conditions of 18.6MPa, the surrosion of alloy is not more than 65mgdm-2；The alloy is placed in into water to steam
It it is 500 DEG C in temperature, pressure is corrodes 500 hours under conditions of 10.3MPa, the surrosion of alloy is not more than in vapour atmosphere
300mg·dm-2。
A kind of nuclear reactor fuel can zirconium-base alloy of above-mentioned fine corrosion resistance, it is characterised in that the conjunction
Gold is made up of the composition of following mass percent：Nb 0.8%~1.2%, V0.01%~0.2%, Fe 0.03%~0.2%,
O 0.07%~0.14%, surplus is Zr and inevitable impurity.
A kind of nuclear reactor fuel can zirconium-base alloy of above-mentioned fine corrosion resistance, it is characterised in that the conjunction
V and Fe mass ratio is 1 in gold: (2~3).
A kind of nuclear reactor fuel can zirconium-base alloy of above-mentioned fine corrosion resistance, it is characterised in that the conjunction
Gold is made up of the composition of following mass percent：Nb 1.05%, V 0.05%, Fe0.11%, O 0.1%, surplus is for Zr and not
Evitable impurity.
A kind of nuclear reactor fuel can zirconium-base alloy of above-mentioned fine corrosion resistance, it is characterised in that the conjunction
Gold is made up of the composition of following mass percent：Nb 1.0%, V 0.1%, Fe 0.2%, O 0.1%, surplus is Zr and can not
The impurity avoided.
A kind of nuclear reactor fuel can zirconium-base alloy of above-mentioned fine corrosion resistance, it is characterised in that the conjunction
Gold is made up of the composition of following mass percent：Nb 1.2%, V 0.06%, Fe 0.15%, O 0.11%, surplus be Zr and
Inevitable impurity.
A kind of nuclear reactor fuel can zirconium-base alloy of above-mentioned fine corrosion resistance, it is characterised in that the conjunction
Gold is made up of the composition of following mass percent：Nb0.9%, V 0.01%, Fe 0.03%, O 0.12%, surplus is for Zr and not
Evitable impurity.
A kind of nuclear reactor fuel can zirconium-base alloy of above-mentioned fine corrosion resistance, it is characterised in that the conjunction
Gold is made up of the composition of following mass percent：Nb 0.8%, V 0.04%, Fe 0.12%, O 0.11%, surplus be Zr and
Inevitable impurity.
The present invention has advantages below compared with prior art：
1st, zirconium-base alloy of the present invention is a kind of iron content, the zirconium-niobium alloy of vanadium, and wherein niobium is a kind of β phases stable element,
Niobium has higher invigoration effect to zirconium, it has been investigated that, when adding a small amount of niobium, the decay resistance of Zirconium alloy material just can
It is improved, but content of niobium is too high that alloy can be caused sensitive for heat treatment, so the addition of niobium is not more than in the present invention
1.5wt%, ensure that zirconium-base alloy has excellent decay resistance and good mechanical property；In addition, oxygen element is in zirconium
Interstitial solid solution can be formed in based alloy, the interstitial solid solution can improve the mechanical strength of alloy, still, too low oxygen content
Improvement is not obvious, does not reach required performance requirement, and low-alloyed machinability, this hair can drop in too high oxygen content
Bright zirconium-niobium alloy oxygen content is 0.07wt%~0.14wt%, and the mechanical strength for improving alloy can be taken into account simultaneously and keeps closing
The good machinability of gold.
2nd, low-alloyed alpha-beta transition temperature, dissolving of the iron in α-Zr can drop in the iron in zirconium-base alloy of the present invention
Degree about 0.02%, maxima solubility in β-Zr is that to add magnetic transition temperature after pure iron in 5.5%, zircaloy be 769
DEG C, the intermetallic compound of formation has Zr2Fe and ZrFe2, wherein ZrFe2With C15 (MgCu2) type structure, closed in zirconium base containing niobium
(Zr, the Nb) Fe generated in gold2Intermediate alloy improves the corrosive nature of alloy, but the iron of too high amount can influence alloy
Processing characteristics, influences the lumber recovery of product, therefore, and the present invention adds a small amount of V in Zr-Nb-Fe alloys, can improve
In the case of alloy corrosion performance, its processing characteristics is not influenceed；Vanadium is usually impurity component in zircaloy, need to control its content
＜ 0.005wt%, but low-alloyed alpha-beta transition temperature can drop in vanadium, and in the present invention, vanadium is added to zirconium as alloying element and closed
Jin Zhong, can optimize its processing characteristics, improves the machinery of zirconium-niobium alloy in the case where improving the excellent decay resistance of alloy
Performance.
3rd, the invention provides a kind of nuclear reactor fuel can zirconium-base alloy, the alloy has excellent corrosion resistance
Can, the alloy is immersed in deionized water, is 360 DEG C in temperature, pressure is corrosion 200 days under conditions of 18.6MPa, alloy
Surrosion is not more than 65mgdm-2；The alloy is placed in deionized water steam atmosphere, is 500 DEG C in temperature, pressure is
Corrode 500 hours under conditions of 10.3MPa, the surrosion of alloy is not more than 300mgdm-2。
The present invention is described in further detail with reference to embodiment.
Embodiment
The composition of the nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance of the present invention is by mass percentage
For：Nb 0.8%~1.5%, V 0.005%~0.2%, Fe 0.005%~0.2%, O0.07%~0.14%, surplus is
Zr and inevitable impurity；It is preferred that into being grouped into：Nb0.8%~1.2%, V 0.01%~0.2%, Fe 0.03%
~0.2%, O 0.07%~0.14%, surplus is Zr and inevitable impurity.V and Fe mass ratio is preferably 1 in alloy:
(2~3).The raw material and preparation technology of zirconium-base alloy of the present invention are routine techniques.Specifically prepare the raw material involved by the alloy
Including core sponge zirconium, ferrozirconium vanadium alloy and zirconium-niobium alloy.The method for specifically preparing the alloy is：First, according to design composition
Raw material is selected, then raw material is smelted into ferrozirconium vanadium intermediate alloy and zirconium niobium intermediate alloy, then, uniform electrode pressing, in vacuum
Alloy cast ingot is obtained after three conventional meltings in consumable electroarc furnace, in forging temperature is 960 DEG C by the alloy cast ingot afterwards
Cogging forging is carried out under conditions of~1000 DEG C, slab is obtained, in temperature is 1010 DEG C~1050 DEG C bars by the slab then
Solution treatment is carried out under part, cold rolling multistage hot deformation, multi-pass, intermediate annealing and finished products work is sequentially passed through after quenching again
Sequence, finally gives zirconium-base alloy sheet material；The temperature of the hot rolling is 590 DEG C~650 DEG C, and the pass deformation of the hot rolling is
60%~85%, the cold rolling pass deformation is 50%~70%, and the intermediate annealing and finished products are in temperature
560 DEG C~600 DEG C, the time is 2h, and vacuum is not more than 8.0 × 10-2Carried out under conditions of Pa.
Embodiment 1
The nuclear reactor fuel can zirconium-base alloy of the present embodiment fine corrosion resistance is by following mass percent
Composition is constituted：Nb 1.05%, V 0.05%, Fe 0.11%, O 0.10%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 980 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1030 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 600 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 70%, then in temperature be 600 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 60% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 600 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 560 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
Embodiment 2
The nuclear reactor fuel can zirconium-base alloy of the present embodiment fine corrosion resistance is by following mass percent
Composition is constituted：Nb 1.0%, V 0.1%, Fe 0.2%, O 0.10%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 960 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1050 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 590 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 70%, then in temperature be 600 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 60% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 600 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 560 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
Embodiment 3
The nuclear reactor fuel can zirconium-base alloy of the present embodiment fine corrosion resistance is by following mass percent
Composition is constituted：Nb 1.2%, V 0.06%, Fe 0.15%, O 0.11%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 1000 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1050 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 590 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 70%, then in temperature be 600 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 60% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 600 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 560 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
Embodiment 4
The nuclear reactor fuel can zirconium-base alloy of the present embodiment fine corrosion resistance is by following mass percent
Composition is constituted：Nb 0.9%, V 0.01%, Fe 0.03%, O 0.12%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 980 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1030 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 650 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 60%, then in temperature be 580 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 60% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 580 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 580 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
Embodiment 5
The nuclear reactor fuel can zirconium-base alloy of the present embodiment fine corrosion resistance is by following mass percent
Composition is constituted：Nb 0.8%, V 0.04%, Fe 0.12%, O 0.11%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 960 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1010 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 650 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 80%, then in temperature be 560 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 50% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 560 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 600 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
Embodiment 6
The present embodiment nuclear reactor fuel can is made up of with zirconium-base alloy the composition of following mass percent：Nb
1.5%, V 0.005%, Fe 0.005%, O 0.10%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 980 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1030 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 580 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 60%, then in temperature be 580 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 55% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 600 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 560 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
Embodiment 7
The present embodiment nuclear reactor fuel can is made up of with zirconium-base alloy the composition of following mass percent：Nb
0.8%, V 0.05%, Fe 0.05%, O 0.14%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 980 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1030 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 600 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 70%, then in temperature be 600 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 60% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 600 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 560 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
Embodiment 8
The present embodiment nuclear reactor fuel can is made up of with zirconium-base alloy the composition of following mass percent：Nb
1.2%, V 0.2%, Fe 0.2%, O 0.07%, surplus is Zr and inevitable impurity.
The preparation method of the present embodiment zirconium-base alloy is：First, according to component selections raw material is designed to, raw material is smelted into zirconium
Ferrovanadium intermediate alloy and zirconium niobium intermediate alloy, uniform electrode pressing are obtained in vacuum consumable electrode arc furnace after three conventional meltings
Cogging forging is carried out under conditions of forging temperature is 980 DEG C to alloy cast ingot, then by the alloy cast ingot, slab is obtained；So
Afterwards, the slab is subjected to solution treatment under the conditions of temperature is 1030 DEG C and quenched；Afterwards, by the slab after quenching first in temperature
Spend for 600 DEG C, pass deformation is to carry out a fire time hot rolling under conditions of 70%, then in temperature be 600 DEG C, vacuum is not more than
8.0×10-2Intermediate annealing 2h under conditions of Pa, then pass deformation be 60% under conditions of carry out it is cold rolling twice, and
Between cold rolling twice temperature be 600 DEG C, vacuum is not more than 8.0 × 10-2Intermediate annealing 2h under conditions of Pa, finally in temperature
For 560 DEG C, vacuum is not more than 8.0 × 10-2Finished products 2h under conditions of Pa, finally gives the zirconium base that thickness is 1.4mm and closes
Golden plate material.
According to national standard《ASTM G2/G2M-2006》" water of the product of zirconium, hafnium and its alloy at 680 °F [360 DEG C]
In or the steam of 750 °F [400 DEG C] in erosion test test method " to existing Zr-4 alloys, (there is coloured gold northwest respectively
Belong to research institute prepare) and the embodiment of the present invention 1~8 preparation nuclear reactor fuel can zirconium-base alloy sheet material corrosive nature
Tested, method of testing is：The nuclear reactor fuel can for respectively preparing Zr-4 alloys and the embodiment of the present invention 1~8 is used
Zirconium-base alloy sheet material is placed in autoclave, and its surrosion is weighed after carrying out corrosion treatment；The condition of the corrosion treatment is：
Temperature is 360 DEG C, and pressure is corrosion in immersion deionized water under conditions of 18.6MPa 200 days；It it is 500 DEG C in temperature, pressure is
It is placed in deionized water steam atmosphere and corrodes 500 hours under conditions of 10.3MPa.Zr-4 alloys and the embodiment of the present invention 1~8 are made
Standby nuclear reactor fuel can is shown in Table 1 with the corrosive nature test result of zirconium-base alloy.
The zirconium-base alloy corrosive nature test result of table 1
As can be seen from Table 1, compared with Zr-4 sheet alloys, nuclear reactor fuel bag prepared by the embodiment of the present invention 1~8
Shell zirconium-base alloy is under conditions of 360 DEG C/18.6MPa/ deionized water/200 day, alloy and 500 DEG C/10.3MPa/ deionizations
Excellent corrosion resistance is respectively provided with conditions of water vapour/500 hour, alloy, wherein, in 360 DEG C/18.6MPa/ deionizations
Under conditions of water/200 day, alloy, the nuclear reactor fuel can of embodiment 1~8 is not more than with the surrosion of zirconium-base alloy
65mg·dm-2；Under conditions of 500 DEG C/10.3MPa/ deionized waters steam/500 hour, alloy, the core of embodiment 1~8 is anti-
Answer the surrosion no more than 300mgdm of heap fuel can zirconium-base alloy-2, Zr-4 alloys far smaller than under the same terms
Surrosion.
The machine of the nuclear reactor fuel can zirconium-base alloy prepared respectively to Zr-4 alloys and the embodiment of the present invention 1~8
Tool performance is tested, and test result is shown in Table 2.
The zirconium-base alloy measuring mechanical property result of table 2
As can be seen from Table 2, the tensile strength of the nuclear reactor fuel can zirconium-base alloy of the embodiment of the present invention 1~8
And yield strength is slightly better than the mechanical performance of Zr-4 alloys, illustrate that the present invention regard a certain proportion of iron, vanadium as alloying element
It is added in zircaloy, not only increases the decay resistance of zircaloy, and optimize its processing characteristics, improves zirconium-niobium alloy
Mechanical performance, zirconium-base alloy of the present invention may be used as the structural material of nuclear reactor fuel can material or nuclear reactor.
It is described above, only it is presently preferred embodiments of the present invention, not the present invention is imposed any restrictions.It is every according to invention skill
Any simple modification, change and equivalence change that art is substantially made to above example, still fall within technical solution of the present invention
Protection domain in.
Claims (6)
1. the nuclear reactor fuel can zirconium-base alloy of a kind of fine corrosion resistance, it is characterised in that the alloy is by following
The composition composition of mass percent：Nb 0.8%~1.2%, V 0.01%~0.2%, Fe 0.03%~0.2%, O
0.07%~0.14%, surplus is Zr and inevitable impurity；V and Fe mass ratio is 1 in the alloy: (2~3)；The conjunction
Gold utensil has excellent decay resistance, is specially：The alloy is immersed in deionized water, is 360 DEG C in temperature, pressure is
Corrode 200 days under conditions of 18.6MPa, the surrosion of alloy is not more than 65mgdm-2；The alloy is placed in water vapour atmosphere
In, it is 500 DEG C in temperature, pressure is corrodes 500 hours under conditions of 10.3MPa, the surrosion of alloy is not more than 300mg
dm-2。
2. a kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance according to claim 1, it is special
Levy and be, the alloy is made up of the composition of following mass percent：Nb 1.05%, V 0.05%, Fe 0.11%, O
0.10%, surplus is Zr and inevitable impurity.
3. a kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance according to claim 1, it is special
Levy and be, the alloy is made up of the composition of following mass percent：Nb 1.0%, V 0.1%, Fe 0.2%, O 0.10%, it is remaining
Measure as Zr and inevitable impurity.
4. a kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance according to claim 1, it is special
Levy and be, the alloy is made up of the composition of following mass percent：Nb 1.2%, V 0.06%, Fe 0.15%, O 0.11%,
Surplus is Zr and inevitable impurity.
5. a kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance according to claim 1, it is special
Levy and be, the alloy is made up of the composition of following mass percent：Nb 0.9%, V 0.01%, Fe 0.03%, O 0.12%,
Surplus is Zr and inevitable impurity.
6. a kind of nuclear reactor fuel can zirconium-base alloy of fine corrosion resistance according to claim 1, it is special
Levy and be, the alloy is made up of the composition of following mass percent：Nb 0.8%, V 0.04%, Fe 0.12%, O 0.11%,
Surplus is Zr and inevitable impurity.
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| CN112195369B (en) * | 2020-11-06 | 2021-07-23 | 西安稀有金属材料研究院有限公司 | Corrosion-resistant high-strength neutron shielding alloy material and preparation method thereof |
| CN113201666A (en) * | 2021-04-08 | 2021-08-03 | 中广核研究院有限公司 | Zirconium alloy for fuel assembly, manufacturing method thereof and cladding tube of fuel assembly |
| CN114703397B (en) * | 2022-03-14 | 2023-10-10 | 西安西部新锆科技股份有限公司 | Zirconium-based alloy with corrosion resistance and creep resistance for nuclear reactor fuel cladding and method for preparing zirconium-based alloy pipe by using zirconium-based alloy |
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| CN104451260A (en) * | 2014-11-29 | 2015-03-25 | 西部新锆核材料科技有限公司 | Iron-manganese-containing zirconium-niobium alloy for nuclear reactor fuel cladding |
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| CN102251151A (en) * | 2011-06-30 | 2011-11-23 | 苏州热工研究院有限公司 | Zirconium alloy material applied to nuclear reactor |
| CN103898362B (en) * | 2012-12-27 | 2016-08-10 | 中国核动力研究设计院 | A kind of water cooled nuclear reactor zirconium-base alloy |
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| CN104451260A (en) * | 2014-11-29 | 2015-03-25 | 西部新锆核材料科技有限公司 | Iron-manganese-containing zirconium-niobium alloy for nuclear reactor fuel cladding |
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