CN102251151A - Zirconium alloy material applied to nuclear reactor - Google Patents
Zirconium alloy material applied to nuclear reactor Download PDFInfo
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- CN102251151A CN102251151A CN2011101801041A CN201110180104A CN102251151A CN 102251151 A CN102251151 A CN 102251151A CN 2011101801041 A CN2011101801041 A CN 2011101801041A CN 201110180104 A CN201110180104 A CN 201110180104A CN 102251151 A CN102251151 A CN 102251151A
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- zirconium alloy
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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
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a zirconium alloy material applied to a nuclear reactor, comprising the following components in percentage based on total weight of a zirconium alloy: N b 0.4%-0.6%, Fe 0.3%-0.4%, Cr 0.2%-0.3%, Cu 0.05%-0.15%, at least one of V 0.01%-0.05% and Ni 0.1%-0.2%, O 0.06%-0.14%, C <=1000 ppm, N <=80 ppm, and the balance of Zr. Research shows that the zirconium alloy disclosed by the invention is excellent in comprehensive performance, particularly good in corrosion resistance in pure water at 360 DEG C and in stream at 400 DEG C; and therefore, the zirconium alloy can be used as a can material of the nuclear reactor.
Description
Technical field
The present invention relates to the Zirconium alloy material field, especially relate to a kind of nuclear pressurized water reactor Zirconium alloy material.
Background technology
The thermal neutron absorption cross section of zirconium is very little, and has good high-temperature resistant water corrosive nature and mechanical property, and therefore zirconium alloy is widely used as the can material of fuel stick and the structural element of nuclear reactor core in water cooled nuclear reactor.Along with the power producer technology develops towards the direction that improves fuel burnup and reduction fuel cycle cost, raising reactor thermo-efficiency, raising safe reliability, to the demands for higher performance such as corrosion resistance, hydrogen sucking function, mechanical property and irradiation dimensional stability of key core parts fuel element can material zirconium alloy.Creep and fatigue under the condition (irradiation, high temperature, high pressure and complicated stress), take place in fuel element under arms.Creep property is one of the major issue that will consider when working in the water-cooled power reactor of zirconium alloy, a large amount of research has been carried out in the creep of zirconium alloy both at home and abroad.At present the most ripe, most widely used is the zirconium alloy that is referred to as Zr-2, Zr-4 alloy, but along with the development of nuclear fuel assembly to long-lived phase, high burnup direction, requirement must have over-all propertieies such as better anti-corrosion, creep resistance, radioprotective growth as the zirconium alloy of reactor structural material, and Zr-2, Zr-4 alloy can not meet the demands in this.
Recent two decades comes, pressurized-water reactor is to having the research of updating and carry out the high-performance new zirconium alloy of material with the research tendency of zirconium alloy, general thought is to carry out the adjustment of alloying constituent content and add other alloying element on Zr-Nb system and Zr-Sn-Nb are the basis of alloy, and perhaps the two carries out simultaneously to reach the purpose of raising alloy monolithic performance.
Summary of the invention
Technical problem to be solved by this invention provides a kind of Zirconium alloy material, and its over-all properties is the corrosion resistance excellence particularly, is suitable for to make nuclear pressurized water reactor structured material.
For solving above technical problem, a kind of technical scheme that the present invention takes is: a kind of Zirconium alloy material that is used for nuclear reactor, gross weight with described Zirconium alloy material is a benchmark, and it is made up of following component: Nb0.4%～0.6%, Fe 0.3%～0.4%, Cr 0.2%～0.3%, Cu 0.05%～0.15%, V 0.01%～0.05%, O 0.06%～0.14%, C≤100ppm, N≤80ppm and Zr surplus.
The another technical scheme that the present invention takes is: a kind of Zirconium alloy material that is used for nuclear reactor, gross weight with described Zirconium alloy material is a benchmark, and it is made up of following component: Nb 0.4%～0.6%, Fe 0.3%～0.4%, Cr 0.2%～0.3%, Cu 0.05%～0.15%, Ni 0.1%～0.2%, 00.06%～0.14%, C≤100ppm, N≤80ppm and Zr surplus.
Perhaps, the present invention also can realize by following scheme: a kind of Zirconium alloy material that is used for nuclear reactor, gross weight with described Zirconium alloy material is a benchmark, and it is made up of following component: Nb 0.4%～0.6%, Fe0.3%～0.4%, Cr 0.2%～0.3%, Cu 0.05%～0.15%, V 0.01%～0.05%, Ni0.1%～0.2%, O 0.06%～0.14%, C≤100ppm, N≤80ppm and Zr surplus.
Preferably, in the zirconium alloy, the content sum of Fe and Ni is 0.45%～0.6%.Studies show that, when the content of Fe and Ni is in this scope, the anti-uniform corrosion better performances of zirconium alloy.
In the above-mentioned alloy formula, C and N unavoidable impurities for from raw material, bringing, one of ordinary skill in the art should be understood, other unavoidable impurities composition that some that may also comprise in the above-mentioned alloy formula are brought from raw material can not cause disadvantageous effect to zirconium alloy of the present invention when these impurity components exist with inevitable amount.
Because the enforcement of above technical scheme, the present invention compared with prior art has the following advantages: the present invention is optimized design to traditional Zr-Nb alloy, the Cr that adds specified quantitative can significantly reduce the corrosion of commissure, the proper C u that adds helps improving corrosion resistance nature, and the introducing of a small amount of V is beneficial to corrosion resistance that improves alloy and the mechanical property of improving alloy; The introducing of small amount of N i is beneficial to corrosion resistance nature that improves alloy and the suction hydrogen that reduces alloy, on above basis, the content that reduces Nb makes and is lower than its limit of solubility in alloy, help alloy to obtain higher yield strength and best creep-resistant property, and the Nb content in this scope can guarantee that zirconium alloy uncontrollable phase transformation can not take place, thereby has improved corrosion resistance nature.Generally speaking, zirconium alloy excellent combination property of the present invention satisfies the requirement of nuclear pressurized water reactor structured material.
Embodiment
The present invention will be further described below in conjunction with specific embodiment, but the invention is not restricted to following examples.
With nuclear level zirconium sponge, Nb, Fe, Cu, Cr, a Ni, V element is prepared burden by mass percentage with the form of master alloy and adopt vacuum arc fumace to carry out repeatedly melting and make alloy pig; Chemical composition analysis is carried out in sampling to ingot casting, and alloying constituent sees Table 1.Ingot casting makes the zirconium alloy sheet material of corresponding composition through operations such as forging, hot rolling, cold rolling, annealing, and is prepared into the corrosion sample and carries out the rotten performance test of autoclave.
Eight kinds of zirconium alloy sheet material and Zr-1Nb sheet alloy to embodiments of the invention 1-8 carry out the corrosive nature test.Corrosion test is carried out in autoclave, and etching condition is 360 ℃/18.6MPa pure water and 400 ℃/10.3MPa steam.Table 1 has provided according to erosion rate and relative erosion rate under the composition proportion of embodiments of the invention 1-8 and their each comfortable above-mentioned etching conditions.9
*Be Zr-1Nb alloy composition and corresponding corrosion test result.
Table 1 alloying constituent and the corrosion data under 360 ℃ of pure water and 400 ℃ of steam conditions thereof
From the data of table 1 as can be seen, alloy of the present invention corrosive nature in 360 ℃/18.6MPa pure water and in the 400 ℃/10.3MPa superheated vapour all significantly is better than the Zr-1Nb alloy, satisfy the power station in addition to the requirement of can material corrosive nature, zirconium alloy mechanical property excellence of the present invention, suction hydrogen is little, and creep property is better.
The foregoing description only is explanation technical conceive of the present invention and characteristics, and its purpose is to allow the personage who is familiar with this technology can understand content of the present invention and enforcement according to this, can not limit protection scope of the present invention with this.All equivalences that spirit is done according to the present invention change or modify, and all should be encompassed within protection scope of the present invention.
Claims (4)
1. Zirconium alloy material that is used for nuclear reactor, it is characterized in that: the gross weight with described Zirconium alloy material is a benchmark, and described Zirconium alloy material is made up of following component: Nb 0.4%～0.6%, Fe 0.3%～0.4%, Cr 0.2%～0.3%, Cu 0.05%～0.15%, V 0.01%～0.05%, O 0.06%～0.14%, C≤100ppm, N≤80ppm and Zr surplus.
2. Zirconium alloy material that is used for nuclear reactor, it is characterized in that: the gross weight with described Zirconium alloy material is a benchmark, and described Zirconium alloy material is made up of following component: Nb 0.4%～0.6%, Fe 0.3%～0.4%, Cr 0.2%～0.3%, Cu 0.05%～0.15%, Ni 0.1%～0.2%, O 0.06%～0.14%, C≤100ppm, N≤80ppm and Zr surplus.
3. Zirconium alloy material that is used for nuclear reactor, it is characterized in that: the gross weight with described Zirconium alloy material is a benchmark, and described Zirconium alloy material is made up of following component: Nb 0.4%～0.6%, Fe 0.3%～0.4%, Cr 0.2%～0.3%, Cu 0.05%～0.15%, V 0.01%～0.05%, Ni 0.1%～0.2%, O 0.06%～0.14%, C≤100ppm, N≤80ppm and Zr surplus.
4. the Zirconium alloy material that is used for nuclear reactor according to claim 3 is characterized in that: in the described Zirconium alloy material, the content sum of Fe and Ni is 0.45%～0.6%.
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| CN2011101801041A CN102251151A (en) | 2011-06-30 | 2011-06-30 | Zirconium alloy material applied to nuclear reactor |
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| CN2011101801041A CN102251151A (en) | 2011-06-30 | 2011-06-30 | Zirconium alloy material applied to nuclear reactor |
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Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105018795A (en) * | 2015-07-31 | 2015-11-04 | 西部新锆核材料科技有限公司 | Zirconium-based alloy for nuclear reactor fuel cladding good in corrosion resistance |
Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5985211A (en) * | 1998-02-04 | 1999-11-16 | Korea Atomic Energy Research Institute | Composition of zirconium alloy having low corrosion rate and high strength |
| CN1818111A (en) * | 2005-02-07 | 2006-08-16 | 韩国原子力研究所 | Zirconium based alloys having excellent creep resistance |
| CN1871371A (en) * | 2003-10-08 | 2006-11-29 | 欧洲塞扎斯“锆”公司 | Method of producing a flat zirconium alloy product, flat product thus obtained and a nuclear plant reactor grid which is made from said flat product |
| CN101270426A (en) * | 2008-03-24 | 2008-09-24 | 中国核动力研究设计院 | Zirconium based alloy for nuclear reactor |
-
2011
- 2011-06-30 CN CN2011101801041A patent/CN102251151A/en active Pending
Patent Citations (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US5985211A (en) * | 1998-02-04 | 1999-11-16 | Korea Atomic Energy Research Institute | Composition of zirconium alloy having low corrosion rate and high strength |
| CN1871371A (en) * | 2003-10-08 | 2006-11-29 | 欧洲塞扎斯“锆”公司 | Method of producing a flat zirconium alloy product, flat product thus obtained and a nuclear plant reactor grid which is made from said flat product |
| CN1818111A (en) * | 2005-02-07 | 2006-08-16 | 韩国原子力研究所 | Zirconium based alloys having excellent creep resistance |
| CN101270426A (en) * | 2008-03-24 | 2008-09-24 | 中国核动力研究设计院 | Zirconium based alloy for nuclear reactor |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN105018795A (en) * | 2015-07-31 | 2015-11-04 | 西部新锆核材料科技有限公司 | Zirconium-based alloy for nuclear reactor fuel cladding good in corrosion resistance |
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Application publication date: 20111123 |