CN101413073A - Magnesium-containing zirconium-niobium alloy for nuclear reactor fuel can - Google Patents
Magnesium-containing zirconium-niobium alloy for nuclear reactor fuel can Download PDFInfo
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- CN101413073A CN101413073A CNA2008102325426A CN200810232542A CN101413073A CN 101413073 A CN101413073 A CN 101413073A CN A2008102325426 A CNA2008102325426 A CN A2008102325426A CN 200810232542 A CN200810232542 A CN 200810232542A CN 101413073 A CN101413073 A CN 101413073A
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Abstract
The invention discloses a magnesium-containing zirconium-niobium alloy for nuclear reactor fuel cladding, which is characterized in that the component content in mass percentage of the alloy is counted as follows: 0.8 to 1.2 percent of Nb, 0.02 to 0.5 percent of Mg, 700 to 1,400 ppm of O and the balance being Zr. The magnesium-zirconium-niobium alloy of the invention has excellent corrosion resisting performance and high strength performance. The magnesium-zirconium-niobium alloy has more excellent corrosion resistance than the prior Zr-4 alloy, and is applicable to cladding materials, gratings and other structural components for reactor fuel rods of nuclear power plants.
Description
Technical field
The invention belongs to the material technology field, relate to a kind of zirconium-based alloy material, particularly relate to a kind of magniferous zirconium-niobium alloy that is used for nuclear reactor fuel can.
Background technology
Zirconium and alloy thereof are widely used in doing in the power producer structure unit and fuel sheath, and this mainly is because zirconium has low thermal neutron absorption cross section, and strong corrosion resistance and high physical strength are arranged in high-temperature water.In nuclear reactor, be to reduce the effective way of nuclear power cost owing to improve the burnup of nuclear fuel, and be the water side corrosion of fuel sheath zirconium alloy and inhale hydrogen for the key constraints that pressurized-water reactor further improves burnup.Therefore, the corrosion resistance of zirconium alloy is had higher requirement.
To achieve these goals, the adding of alloying element should be satisfied (1) thermal neutron absorption cross section should be little, could keep the low advantage of thermal neutron absorption cross section of zirconium; (2) alloying element should guarantee the corrosion resisting property of structure unit in the reactor whole service phase in longevity that this alloy is made.(3) alloying element should guarantee the structure unit that this alloy is made, and mechanics is stable and reliable for performance under the various possibility operating modes of reactor operation.Main at present zirconium alloy-2, zirconium alloy-4, M5 alloy, E635 alloy, the ZIRLO alloy etc. of using.
According to pertinent literature, generally all contain metallic elements such as minor N b, Sn, Cr, Fe in the zirconium alloy composition of the existing trade mark at present.For example the Zr-2 alloy contains the Sn of 1.2-1.7wt%, 0.07-0.2wt% Fe, 0.05-0.15wt% Cr, 0.03-0.08wt% Ni, 0.08-0.15 wt% O; The Zr-4 alloy contains 1.2-1.7wt% Sn, 0.18-0.24wt% Fe, 0.07-0.13wt% Cr, 0.07wt%Ni, 0.08-0.15wt% O; The E635 zirconium alloy contains 1.2-1.3wt% Sn, 0.34-0.4wt% Fe, 0.95-1.05wt% Nb; The zirconium base alloy of U.S. Pat 4649023 disclosed commodity ZIRLO by name contains 0.7-1.5wt% Sn, 0.07-0.14wt% Fe, 0.5-2.0wt% Nb; The M5 zirconium alloy contains 0.8-1.2wt% Nb, 0.09-0.15wt% O; The NDA zirconium alloy contains 1.0wt% Sn, 0.28wt% Fe, 0.16wt% Cr, 0.01wt% Ni, 0.10wt% Nb.
In sum, add suitable alloying element and set of dispense than being to develop to have one of higher corrosion resistance nature and mechanical property new zirconium alloy approach.For this reason, the present invention proposes new alloying constituent by research alloy compositions proportioning, and exploitation has the more zirconium alloy of good corrosion resistance.
Summary of the invention
The objective of the invention is in order to overcome the deficiencies in the prior art, a kind of magniferous zirconium-niobium alloy that is used for nuclear reactor fuel can with excellent corrosion resistance is provided, this zirconium base alloy is applicable to the structured material and the fuel sheath element of nuclear reactor.
For solving the problems of the technologies described above, the technical solution used in the present invention is: a kind of magniferous zirconium-niobium alloy that is used for nuclear reactor fuel can is characterized in that this alloying constituent content is by mass percentage: Nb0.8-1.2%, Mg0.02-0.5%, O 700ppm-1400ppm, surplus is Zr.
Details are as follows now the present invention to be determined the reason of each element and consumption:
Nb: known Nb is a kind of β phase stable element in the zirconium.Niobium has higher strengthening effect to zirconium.Studies show that, when adding the Nb of a small amount of (less than 0.15%), the corrosion resistance nature of Zirconium alloy material just can be improved, when the Nb content height to 1.2% that adds, the corrosion resistance nature of alloy also can be greatly improved, and the mechanics and the anti-hydrogen sucking function of alloy also are improved simultaneously simultaneously.
The O:O element can form interstitial solid solution in zirconium alloy, this sosoloid can improve the alloy physical strength, and still, the strengthening effect of crossing low O content is not obvious, do not reach required performance requriements, and too high O content can reduce the workability of alloy.The determined optimum content scope of the present invention is 700-1400ppm.
Mg:Mg has lower thermal neutron absorption cross section, is solid-solubilized in the zirconium alloy matrix, adds the corrosion resistance nature that a spot of Mg can improve zirconium alloy, and reduces hydrogen, reduces the formation of hydride thus, and this hydride can cause material to become fragile.
The present invention compared with prior art has the following advantages: the magniferous zirconium-niobium alloy of the present invention has excellent corrosion resistance, this magniferous zirconium-niobium alloy has better solidity to corrosion than existing Zr-4 alloy, is applicable to can material, grid and other construction package of nuclear power plant reactor fuel stick.
The invention will be further described below in conjunction with specific embodiment, and embodiment is just to explanation of the present invention and non-limiting.
Embodiment
Embodiment
A kind of magniferous zirconium-niobium alloy that is used for nuclear reactor fuel can, this alloying constituent content is by mass percentage: Nb0.8-1.2%, Mg0.02-0.5%, O 700ppm-1400ppm, surplus is Zr.
Its preparation method is:
(1) is pressed into electrode with nuclear level zirconium sponge and nuclear level pure metal raw material by above-mentioned prescription batching, carries out three meltings, make alloy pig at vacuum consumable electrode arc furnace.
(2) alloy pig in the step (1) is forged extrusion processing under 900-1050 ℃ of temperature and become the base material; The base material is again through quenching after 1020-1060 ℃ of solution treatment of high temperature.
(3) the base material after quenching is made sheet material after repeatedly cold rolling, hot rolling and process annealing, and sheet material makes Zirconium alloy material after 580 ℃ of temperature recrystallization annealing.
Characteristics in the embodiment of the invention are: 1) special alloy formula; 2) all annealing temperatures all are no more than 600 ℃, and the big strain complete processing of low temperature helps forming second phase that small and dispersed distributes, and further improves the corrosion resistance nature of zirconium alloy.
6 kinds of zirconium base alloy sheet materials that the embodiment of the invention is obtained have carried out the corrosive nature test.Corrosion test is carried out at autoclave, and etching condition is 360 ℃, 18.6MPa deionized water; 400 ℃, 10.3MPa deionized water steam, etching time is 100 days.Table 1 has provided the erosion rate of every kind of zirconium base alloy, and as a comparison, the testing data of the same test conditions of Zr-4 alloy is listed in table 1 too.
Table 1
Claims (1)
1, a kind of magniferous zirconium-niobium alloy that is used for nuclear reactor fuel can, it is characterized in that: this alloying constituent content is by mass percentage: Nb 0.8-1.2%, Mg 0.02-0.5%, O700ppm-1400ppm, surplus is Zr.
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| CN2008102325426A CN101413073B (en) | 2008-12-03 | 2008-12-03 | Magnesium-containing zirconium-niobium alloy for nuclear reactor fuel can |
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| CN101413073A true CN101413073A (en) | 2009-04-22 |
| CN101413073B CN101413073B (en) | 2011-03-16 |
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Cited By (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101805842A (en) * | 2010-03-31 | 2010-08-18 | 西北有色金属研究院 | Zirconium-tin-niobium corrosion-resistant zirconium-base alloy for nuclear fuel cans |
| 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 |
| CN105296803A (en) * | 2015-12-07 | 2016-02-03 | 西部新锆核材料科技有限公司 | Zirconium niobium alloy for nuclear reactor fuel cladding and preparation method thereof |
| CN105385896A (en) * | 2015-12-08 | 2016-03-09 | 西部新锆核材料科技有限公司 | Corrosion-resistant zirconium-tin-niobium alloy for nuclear reactor core and preparing method of corrosion-resistant zirconium-tin-niobium alloy |
| WO2022213543A1 (en) * | 2021-04-08 | 2022-10-13 | 中广核研究院有限公司 | Zirconium alloy and manufacturing method therefor, cladding tube, and fuel assembly |
-
2008
- 2008-12-03 CN CN2008102325426A patent/CN101413073B/en active Active
Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN101805842A (en) * | 2010-03-31 | 2010-08-18 | 西北有色金属研究院 | Zirconium-tin-niobium corrosion-resistant zirconium-base alloy for nuclear fuel cans |
| 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 |
| CN104451260B (en) * | 2014-11-29 | 2016-06-29 | 西部新锆核材料科技有限公司 | A kind of nuclear reactor fuel can zirconium-niobium alloy containing ferrimanganic |
| CN105296803A (en) * | 2015-12-07 | 2016-02-03 | 西部新锆核材料科技有限公司 | Zirconium niobium alloy for nuclear reactor fuel cladding and preparation method thereof |
| CN105385896A (en) * | 2015-12-08 | 2016-03-09 | 西部新锆核材料科技有限公司 | Corrosion-resistant zirconium-tin-niobium alloy for nuclear reactor core and preparing method of corrosion-resistant zirconium-tin-niobium alloy |
| CN105385896B (en) * | 2015-12-08 | 2017-11-24 | 西部新锆核材料科技有限公司 | A kind of nuclear reactor corrosion-resistant zirconium tin niobium alloy and preparation method thereof |
| WO2022213543A1 (en) * | 2021-04-08 | 2022-10-13 | 中广核研究院有限公司 | Zirconium alloy and manufacturing method therefor, cladding tube, and fuel assembly |
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| CN101413073B (en) | 2011-03-16 |
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Effective date of registration: 20130508 Address after: Economic and Technological Development Zone Jingwei Metro New Material Industrial Park in Shaanxi Province Jing high road 710200 in the middle of Xi'an City Patentee after: WESTERN ENERGY MATERIAL TECHNOLOGIES CO.,LTD. Address before: 710016 Shaanxi province Xi'an Weiyang Weiyang Road No. 96 Patentee before: NORTHWEST INSTITUTE FOR NONFERROUS METAL RESEARCH |
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Address after: 710299 No. 19, east section of Jinggao North Road, Jingwei new town, Xi'an Economic and Technological Development Zone, Xi'an City, Shaanxi Province Patentee after: Xi'an Western New Zirconium Technology Co.,Ltd. Address before: 710,200 Middle section of Jinggao West Road, Jingwei New City New Material Industrial Park, Xi'an Economic and Technological Development Zone, Shaanxi Province Patentee before: WESTERN ENERGY MATERIAL TECHNOLOGIES CO.,LTD. |
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