CN102220521B - Zirconium alloy for nuclear reactor - Google Patents
Zirconium alloy for nuclear reactor Download PDFInfo
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- CN102220521B CN102220521B CN201110147676XA CN201110147676A CN102220521B CN 102220521 B CN102220521 B CN 102220521B CN 201110147676X A CN201110147676X A CN 201110147676XA CN 201110147676 A CN201110147676 A CN 201110147676A CN 102220521 B CN102220521 B CN 102220521B
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- zircaloy
- zirconium alloy
- nuclear reactor
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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
Abstract
The invention discloses a zirconium alloy for a nuclear reactor, comprises the following ingredients which take the total weight of the zirconium alloy as reference: Nb 0.2-0.4wt%, Sn 0.4-0.6wt%, Fe 0.3-0.5wt%, Cr 0.2-0.3wt%, V 0.1-0.3wt%, O 600-1200ppm, C less than or equal to 100ppm, N less than or equal to 80ppm and the balance being made up of Zr, wherein, the weight ratio of Nb to Fe is less than or equal to 1, and the weight ratio of Fe to Cr is 1.4-1.6:1. The present formula of zirconium alloy is optimized by the invention, so that when the content of Sn is small, the zirconium alloy still has excellent corrosion resistance and good mechanical property.
Description
Technical field
the present invention relates to the Zirconium alloy material field, especially relate to the corrosion-resistant zircaloy of a kind of energy as the fuel rod clad material in light-water nuclear power plant nuclear reactor.
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 in water cooled nuclear reactor, zircaloy is widely used as the cladding materials of fuel rod and the structural detail of nuclear reactor core.Along with the power producer technology, towards the future development that improves fuel burn-up and reduction fuel cycle cost, the raising reactor thermal efficiency, raising safe reliability, the performances such as corrosion resistance, hydrogen sucking function, mechanical property and irradiation dimensional stability of key core parts can material zirconium alloy are had higher requirement.Creep and fatigue under condition (irradiation, high temperature, high pressure and complicated stress), occur in fuel element under arms.Croop property is one of the major issue that will consider while working in the water-cooled power reactor of zircaloy, the creep of zircaloy has been carried out to a large amount of research both at home and abroad.The sixties in last century zircaloy that early development goes out as the Zr-4 alloy, it has excellent physical strength, creep resistance, heat conductivity and low neutron-absorption cross-section under the reactor working temperature, and uses so far widely.Because the burnup design load of the satisfied fuel for nuclear power plant of the Zr-4 alloy institute energy of conventional Zr-Sn system is generally 33GWd/tU, therefore, in order to meet the requirement of high burnup and long-life reactor core, on the one hand, all carried out from many countries since 20 century 70s the corrosion research that improves the Zr-4 alloy, research can better novel zirconium alloy on the other hand, the exploitation of novel zirconium alloy tends to reduce or eliminate the content of tin (Sn), wherein the most outstanding achievement is to have developed low tin Zr-4 alloy, or being referred to as to optimize the Zr-4 alloy, design burn-up can reach 45GWd/tU.
chinese invention patent application 200810084446.1 discloses the zirconium-base alloy for nuclear reactor, wherein discloses a kind of alloy component as follows: Sn 0.65%～1.2%; Nb 0.2%～0.45%, Fe 0.2%～0.4%, Cr 0.01%～0.2%, O 0.06%～0.15%, V 0.002%～0.2%, and C 0.012～0.015%, and N0.006%～0.008% and surplus are Zr.This zircaloy has good anti-all even Nodular Corrosions, has higher creep resistant and fatigability, has anti-irradiation growth performance.Although it is above-mentioned that this alloy has advantages of, tin content is still higher.
Summary of the invention
technical matters to be solved by this invention is to overcome the deficiencies in the prior art, and the low tin zircaloy for the nuclear reactor cladding materials that a kind of tin content is lower is provided, and it has good corrosion resistivity and good mechanical property.
for solving above technical matters, the technical solution used in the present invention is:
a kind of used by nuclear reactor zircaloy, the general assembly (TW) of described zircaloy of take is benchmark, described zircaloy is comprised of following component: Nb 0.2%～0.4%, Sn 0.4%～0.6%, Fe 0.3%～0.5%, Cr 0.2%～0.3%, V 0.1%～0.3%, O 600～1200ppm, C≤100ppm, N≤80ppm and Zr surplus, wherein, the weight ratio of Nb and Fe≤1, the weight ratio of Fe and Cr is 1.4～1.6:1.
according to further scheme of the present invention: in described zircaloy, the content summation of Nb, Sn, Fe, Cr, V is no more than 1.5%.Preferably zircaloy consists of: by weight, and Nb 0.3%, Sn 0.5%, Fe 0.35%, Cr 0.25%, V 0.1%～0.15%, O 600 ~ 1200ppm, C≤100ppm, N≤80ppm and Zr surplus.
in above-mentioned alloy formula, C and the N inevitable impurity for bringing from raw material, one of ordinary skill in the art should be understood, other inevitable impurity component that some that may also comprise in above-mentioned alloy formula are brought from raw material, can not cause adverse effect to zircaloy of the present invention when these impurity components exist inevitably to measure.
the present invention compared with prior art has the following advantages: the present invention is optimized design to existing zircaloy formula, makes at Sn content hour, still has excellent corrosion resistivity and good mechanical property.
Embodiment
below in conjunction with specific embodiment, the present invention will be further described, but the invention is not restricted to following examples:
prepare burden by mass percentage with the form of intermediate alloy and adopt vacuum arc furnace ignition to carry out repeatedly melting with core level sponge zirconium (Zr content is greater than 97%), Nb, Sn, Fe, Cr, V element and make alloy pig; To ingot casting, chemical composition analysis is carried out in sampling, and alloying component is in Table 1.Ingot casting makes the zircaloy 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 zircaloy sheet materials to embodiments of the invention 1-8 carry out the corrosive nature test.Corrosion test is carried out in autoclave, and etching condition is 400 ℃, 10.3MPa deionized water steam and 427 ℃ of deionized water steam.Table 1 has provided according to corrosion rate and relative corrosion rate under the composition proportion of the zircaloy of embodiments of the invention 1-8 and their each comfortable above-mentioned etching conditions.
the zircaloy of table 1 embodiment 1-8 forms and decay resistance
from the data of table 1, can find out, zircaloy of the present invention in 427 ℃ of steam corrosion rate lower than 1.15mg/ (dm
2
* d), in 400 ℃ of steam, corrosion rate is less than 0.55 mg/ (dm
2
* d), corrosion resistance excellent (significantly due to low tin Zr-4 alloy and reach and be better than the disclosed corrosive nature of patented claim 00810084446.1).In addition, zircaloy of the present invention has also shown the excellent mechanical properties such as welding characteristic, meets the requirement of power station to the cladding materials corrosive nature.
above-described embodiment is only explanation technical conceive of the present invention and characteristics, and its purpose is to allow the person skilled in the art can understand content of the present invention and implement according to this, can not limit the scope of the invention with this.All equivalences that Spirit Essence is done according to the present invention change or modify, within all should being encompassed in protection scope of the present invention.
Claims (1)
1. a used by nuclear reactor zircaloy, it is characterized in that: by weight, the consisting of of described zircaloy: Nb 0.3%, Sn 0.5%, Fe 0.35%, Cr 0.25%, V 0.1～0.15%, O 600～1200ppm, C≤100ppm, N≤80ppm and Zr surplus.
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| CN201110147676XA CN102220521B (en) | 2011-06-02 | 2011-06-02 | Zirconium alloy for nuclear reactor |
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| CN201110147676XA CN102220521B (en) | 2011-06-02 | 2011-06-02 | Zirconium alloy for nuclear reactor |
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| CN102220521A CN102220521A (en) | 2011-10-19 |
| CN102220521B true CN102220521B (en) | 2013-01-16 |
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| 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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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101270426A (en) * | 2008-03-24 | 2008-09-24 | 中国核动力研究设计院 | Zirconium based alloy for nuclear reactor |
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| KR100382997B1 (en) * | 2001-01-19 | 2003-05-09 | 한국전력공사 | Method of Manufacturing A Tube and A Sheet of Niobium-containing Zirconium Alloys for High Burn-up Nuclear Fuel |
| KR20080074568A (en) * | 2007-02-09 | 2008-08-13 | 한국원자력연구원 | High fe contained zirconium alloy compositions having excellent corrosion resistance and preparation method thereof |
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| CN101270426A (en) * | 2008-03-24 | 2008-09-24 | 中国核动力研究设计院 | Zirconium based alloy for nuclear reactor |
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Address after: 215004 West Ring Road, Jiangsu, Suzhou, No. 1788 Patentee after: Suzhou Nuclear Power Research Institute Co., Ltd. Patentee after: China General Nuclear Power Corporation Address before: 215004 West Ring Road, Jiangsu, Suzhou, No. 1788 Patentee before: Suzhou Nuclear Power Research Institute Co., Ltd. Patentee before: China Guangdong Nuclear Power Group Co., Ltd. |