CN102251150A - Zirconium alloy for nuclear reactor - Google Patents
Zirconium alloy for nuclear reactor Download PDFInfo
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- CN102251150A CN102251150A CN2011101800937A CN201110180093A CN102251150A CN 102251150 A CN102251150 A CN 102251150A CN 2011101800937 A CN2011101800937 A CN 2011101800937A CN 201110180093 A CN201110180093 A CN 201110180093A CN 102251150 A CN102251150 A CN 102251150A
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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
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- 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 for a nuclear reactor. On the basis of the total weight of the zirconium alloy, the zirconium alloy comprises 0.25-0.35% of Nb, 0.35-0.45% of Sn, 0.15-0.35% of Fe, 600-1400 ppm of O, at most 100 ppm of C, at most 80 ppm of N and the balance of Zr, wherein one or more of 0.2-0.3% of Cr, 0.01-0.1% of V and 0.01-0.1% of Cu is/are optionally added. A series of experimental data indicates that compared with the existing low-tin Zr-4 alloy, the zirconium alloy disclosed by the invention has better corrosion resistance in 400 DEG C and 427 DEG C high temperature steam, and satisfies the application demands for the nuclear reactor can material.
Description
Technical field
The present invention relates to the Zirconium alloy material field, especially relate to the corrosion-resistant zirconium alloy of a kind of energy as the fuel rod clad material in the 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 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.Early development goes out in the sixties in last century zirconium alloy such as 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 fuel for nuclear power plant that the Zr-4 alloy that conventional Zr-Sn is can satisfy is generally 33GWd/tU, therefore, in order to satisfy the requirement of high burnup and long lifetime reactor core, on the one hand, many countries have all carried out the corrosion research that improves the Zr-4 alloy since the seventies in 20th century, study the better novel zirconium alloy of performance 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 that is used for nuclear reactor, and it is as follows wherein to disclose a kind of alloy component: 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 zirconium alloy has good anti-all even nodular corrosion performance, has higher creep resistance and fatigability, has anti-irradiation growth performance.Though this alloy has above-mentioned advantage, tin content is still higher.
Summary of the invention
Technical problem to be solved by this invention is to overcome the deficiencies in the prior art, provides the lower nuclear reactor can material of a kind of tin content with hanging down the tin zirconium alloy, and it has good erosion resistance and good mechanical performance.
For solving above technical problem, a kind of technical scheme that the present invention adopts is: a kind of used by nuclear reactor zirconium alloy, gross weight with described zirconium alloy is a benchmark, and it is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, Cr 0.2%～0.3%, O 600～1400ppm, C≤100ppm, N≤80ppm and Zr surplus.
The another technical scheme that the present invention also takes is: a kind of used by nuclear reactor zirconium alloy, gross weight with described zirconium alloy is a benchmark, described zirconium alloy is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, Cr 0.2%～0.3%, V or Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
Another technical scheme that the present invention also takes is: a kind of used by nuclear reactor zirconium alloy, gross weight with described zirconium alloy is a benchmark, it is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, V or Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
Perhaps, the present invention also can realize by following scheme: a kind of used by nuclear reactor zirconium alloy, gross weight with described zirconium alloy is a benchmark, it is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, V 0.01%～0.1%, Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
The present invention can also take following scheme: a kind of used by nuclear reactor zirconium alloy, gross weight with described zirconium alloy is a benchmark, it is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe0.15%～0.35%, Cr 0.2%～0.3%, V 0.01%～0.1%, Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
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.
The present invention compared with prior art has the following advantages: the present invention is optimized design to existing zirconium alloy prescription, makes at Sn content hour still have excellent erosion resistance and good mechanical performance.
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 (Zr content is greater than 97%), Fe, Cr, V, Nb, a Sn, the Cu 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.
Eight kinds of zirconium alloy sheet material and the low tin Zr-4 alloy of Comparative Examples 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 superheated vapour and 427 ℃/10.3MPa superheated vapour.Table 1 has provided according to embodiments of the invention 1-8 and the composition proportion of the zirconium alloy of the low tin Zr-4 alloy of Comparative Examples and erosion rate and the relative erosion rate under their each comfortable above-mentioned etching conditions.
The composition of the low tin Zr-4 alloy of the zirconium alloy of table 1 embodiment 1-8 and Comparative Examples
And the corrosion data in 400 ℃ of superheated vapours and 427 ℃ of superheated vapours
From the data of table 1 as can be seen, zirconium alloy of the present invention erosion rate in 427 ℃ of steam is lower than 1.15mg/ (dm
2* d), erosion rate is less than 0.65mg/ (dm in 400 ℃ of steam
2* corrosion resistance excellence d).In addition, zirconium alloy of the present invention has also shown excellent mechanical properties such as welding characteristic, satisfies the requirement of power station to the can material corrosive nature.
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 (5)
1. used by nuclear reactor zirconium alloy, it is characterized in that: the gross weight with described zirconium alloy is a benchmark, and described zirconium alloy is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, Cr 0.2%～0.3%, O 600～1400ppm, C≤100ppm, N≤80ppm and Zr surplus.
2. used by nuclear reactor zirconium alloy, it is characterized in that: the gross weight with described zirconium alloy is a benchmark, described zirconium alloy is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, Cr 0.2%～0.3%, V or Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
3. used by nuclear reactor zirconium alloy, it is characterized in that: the gross weight with described zirconium alloy is a benchmark, described zirconium alloy is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, V or Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
4. used by nuclear reactor zirconium alloy, it is characterized in that: the gross weight with described zirconium alloy is a benchmark, described zirconium alloy is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, V 0.01%～0.1%, Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
5. used by nuclear reactor zirconium alloy, it is characterized in that: the gross weight with described zirconium alloy is a benchmark, described zirconium alloy is made up of following component: Nb 0.25%～0.35%, Sn 0.35%～0.45%, Fe 0.15%～0.35%, Cr 0.2%～0.3%, V 0.01%～0.1%, Cu 0.01%～0.1%, O 600～1400ppm, C≤100ppm, N≤80ppm, and Zr surplus.
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| CN2011101800937A CN102251150A (en) | 2011-06-30 | 2011-06-30 | Zirconium alloy for nuclear reactor |
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| CN2011101800937A CN102251150A (en) | 2011-06-30 | 2011-06-30 | Zirconium alloy for nuclear reactor |
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Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN103898367A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium-based alloy for nuclear reactor core |
| CN103898365A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium-based alloy for water-cooled nuclear reactor |
| CN103898362A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium-based alloy for water-cooled nuclear reactor |
| CN103898360A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium alloy for nuclear reactor core |
| CN103898369A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium alloy for nuclear reactor |
| CN105568056A (en) * | 2016-01-06 | 2016-05-11 | 中国核动力研究设计院 | Zirconium alloy for pressurized water reactor fuel element cladding |
| 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 |
| 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 |
| CN110284027A (en) * | 2019-08-06 | 2019-09-27 | 中国核动力研究设计院 | A kind of zirconium-base alloy of alkali resistance water quality corrosion |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20020136347A1 (en) * | 2001-01-19 | 2002-09-26 | Jeong Yong Hwan | Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel |
| 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 CN2011101800937A patent/CN102251150A/en active Pending
Patent Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US20020136347A1 (en) * | 2001-01-19 | 2002-09-26 | Jeong Yong Hwan | Method for manufacturing a tube and a sheet of niobium-containing zirconium alloy for a high burn-up nuclear fuel |
| 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 (13)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| 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 |
| CN103898365A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium-based alloy for water-cooled nuclear reactor |
| CN103898362A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium-based alloy for water-cooled nuclear reactor |
| CN103898360A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium alloy for nuclear reactor core |
| CN103898369A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium alloy for nuclear reactor |
| CN103898367A (en) * | 2012-12-27 | 2014-07-02 | 中国核动力研究设计院 | Zirconium-based alloy for nuclear reactor core |
| CN103898360B (en) * | 2012-12-27 | 2016-08-31 | 中国核动力研究设计院 | A kind of nuclear reactor core zircaloy |
| CN105568056A (en) * | 2016-01-06 | 2016-05-11 | 中国核动力研究设计院 | Zirconium alloy for pressurized water reactor fuel element cladding |
| CN105568056B (en) * | 2016-01-06 | 2020-08-25 | 中国核动力研究设计院 | Zirconium alloy for pressurized water reactor fuel element cladding |
| 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 |
| CN110284027A (en) * | 2019-08-06 | 2019-09-27 | 中国核动力研究设计院 | A kind of zirconium-base alloy of alkali resistance water quality corrosion |
| CN110284027B (en) * | 2019-08-06 | 2020-04-21 | 中国核动力研究设计院 | Zirconium-based alloy resistant to alkaline water corrosion |
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Application publication date: 20111123 |