|
|
Nb含量对 Zr-xNb-0.4Sn-0.3Fe合金耐腐蚀性能的影响 |
杨忠波,赵文金( ),程竹青,邱军,张海,卓洪 |
中国核动力研究设计院反应堆燃料及材料重点实验室 成都 610213 |
|
Effect of Nb Content on the Corrosion Resistance of Zr-xNb-0.4Sn-0.3Fe Alloys |
Zhongbo YANG,Wenjin ZHAO( ),Zhuqing CHENG,Jun QIU,Hai ZHANG,Hong ZHUO |
Reactor Fuel and Material Key Laboratory, Nuclear Power Institute of China, Chengdu 610213, China |
引用本文:
杨忠波,赵文金,程竹青,邱军,张海,卓洪. Nb含量对 Zr-xNb-0.4Sn-0.3Fe合金耐腐蚀性能的影响[J]. 金属学报, 2017, 53(1): 47-56.
Zhongbo YANG,
Wenjin ZHAO,
Zhuqing CHENG,
Jun QIU,
Hai ZHANG,
Hong ZHUO.
Effect of Nb Content on the Corrosion Resistance of Zr-xNb-0.4Sn-0.3Fe Alloys[J]. Acta Metall Sin, 2017, 53(1): 47-56.
[1] | Xie X F, Zhang J L, Zhu L, et al.Study on the corrosion resistance of Zr-0.7Sn-0.35Nb-0.3Fe-xGe alloy in lithiated water at high temperature under high pressure[J]. Acta Metall. Sin., 2012, 48: 1487 | [1] | (谢兴飞, 张金龙, 朱莉等. Zr-0.7Sn-0.35Nb-0.3Fe-xGe合金在高温高压LiOH水溶液中耐腐蚀性能的研究[J]. 金属学报, 2012, 48: 1487) | [2] | Pan G, Garde A M, Atwood A R.Performance and property evaluation of high-burnup optimized ZIRLOTM cladding [A]. Zirconium in the Nuclear Industry: 17th International Symposium[C]. West Conshohocken, PA: ASTM International, 2015: 607 | [3] | Shishov V N, Markelov V A, Nikulina A V, et al.Corrosion, dimensional stability and microstructure of VVER-1000 E635 alloy FA components at burnups up to 72 MW day/kgU [A]. Zirconium in the Nuclear Industry: 17th International Symposium[C]. West Conshohocken, PA: ASTM International, 2015: 628 | [4] | Zhou B X, Yao M Y, Li Z K, et al.Optimization of N18 zirconium alloy for fuel cladding of water reactors[J]. J. Mater. Sci. Technol., 2012, 28: 606 | [5] | Garde A M, Comstock R J, Pan G, et al.Advanced zirconium alloy for PWR application [A]. Zirconium in the Nuclear Industry: 16th International Symposium[C]. West Conshohocken, PA: ASTM International, 2011: 784 | [6] | Kim H G, Jeong Y H, Kim T H.Effect of isothermal annealing on the corrosion behavior of Zr-xNb alloys[J]. J. Nucl. Mater., 2004, 326: 125 | [7] | Kim H G, Park J Y, Jeong Y H.Ex-reactor corrosion and oxide characteristics of Zr-Nb-Fe alloys with the Nb/Fe ratio[J]. J. Nucl. Mater., 2005, 345: 1 | [8] | Wei J, Frankel P, Polatidis E, et al.The effect of Sn on autoclave corrosion performance and corrosion mechanisms in Zr-Sn-Nb alloys[J]. Acta Mater., 2013, 61: 4200 | [9] | Müller S, Lanzani L.Corrosion of Zr-1Nb and Zr-2.5Nb in 0.1 M LiOH at 343 ℃[J]. Proc. Mater. Sci., 2015, 8: 46 | [10] | Zhang H X, Li Z K, Zhou L, et al.Effects of structure and internal stresses in oxide films on corrosion mechanism of new zirconium alloy[J]. Acta Metall. Sin., 2014, 50: 1529 | [10] | (章海霞, 李中奎, 周廉等. 氧化膜结构及内应力对新锆合金腐蚀机理的影响[J]. 金属学报, 2014, 50: 1529) | [11] | Wei T G, Long C S, Miao Z, et al.Corrosion behavior of Zr-0.4Fe-1.0Cr-xMo alloys in 500 ℃ and 10.3 MPa steam[J]. Acta Metall. Sin., 2013, 49: 717(韦天国, 龙冲生, 苗志等. Zr-0.4Fe-1.0Cr-xMo合金在500 ℃和10.3 MPa水蒸汽中的腐蚀行为 [J]. 金属学报, 2013, 49: 717) | [12] | Platt P, Frankel P, Gass M, el al. Critical assessment of finite element analysis applied to metal-oxide interface roughness in oxidising zirconium alloys[J]. J. Nucl. Mater., 2015, 464: 313 | [13] | Platt P, Polatidis E, Frankel P, et al.A study into stress relaxation in oxides formed on zirconium alloys[J]. J. Nucl. Mater., 2015, 456: 415 | [14] | Shishov V N.The evolution of microstructure and deformation stability in Zr-Nb-(Sn, Fe) alloys under neutron irradiation [A]. Zirconium in the Nuclear Industry: 16th International Symposium[C]. West Conshohocken, PA: ASTM International, 2011: 37 | [15] | Garner A, Gholinia A, Frankel P, et al.The microstructure and microtexture of zirconium oxide films studied by transmission electron backscatter diffraction and automated crystal orientation mapping with transmission electron microscopy[J]. Acta Mater., 2014, 80: 159 | [16] | Yang Z B, Zhao W J, Miao Z, et al.Corrosion behavior of Zr-XSn-1Nb-0.3Fe(X=0~1.5) alloys[J]. Rare Met. Mater. Eng., 2015, 44: 1129 | [16] | (杨忠波, 赵文金, 苗志等. Zr-XSn-1Nb-0.3Fe(X=0~1.5)合金的腐蚀行为研究[J]. 稀有金属材料与工程, 2015, 44: 1129) | [17] | Guo X C, Luan B F, Chen J W, et al.Distribution characteristics of precipitation of N18 zirconium alloy[J]. Rare Met. Mater. Eng., 2011, 40: 813 | [17] | (过锡川, 栾佰峰, 陈建伟等. N18锆合金沉淀相分布特征的研究[J]. 稀有金属材料与工程, 2011, 40: 813) | [18] | Preuss M, Frankel P, Lozano-Perez S, et al.Studies regarding corrosion mechanisms in zirconium alloys [A]. Zirconium in the Nuclear Industry: 16th International Symposium[C]. West Conshohocken, PA: ASTM International, 2011: 649 | [19] | Li S L, Yao M Y, Zhang X, et al.Effect of adding Cu on the corrosion resistance of M5 alloy in superheated steam at 500 ℃[J]. Acta Metall. Sin., 2011, 47: 163 | [19] | (李士炉, 姚美意, 张欣等. 添加Cu对M5合金在500 ℃过热蒸汽中耐腐蚀性能的影响[J]. 金属学报, 2011, 47: 163) | [20] | Mardon J P, Charquet D, Senevat J.Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy [A]. Zirconium in the Nuclear Industry: 12th International Symposium[C]. West Conshohocken, PA: ASTM International, 2000: 505 | [21] | Couet A, Motta A T, Comstock R J.Effect of alloying elements on hydrogen pickup in zirconium alloys [A]. Zirconium in the Nuclear Industry: 17th International Symposium[C]. West Conshohocken, PA: ASTM International, 2015: 479 | [22] | Chabretou V, Hoffmann P B, Trapp-Pritsching S, et al.Ultra low tin quaternary alloys PWR performance-impact of tin content on corrosion resistance, irradiation growth, and mechanical properties [A]. Zirconium in the Nuclear Industry: 16th International Symposium[C]. West Conshohocken, PA: ASTM International, 2011: 801 | [23] | Wikmark G, Rudling P, Lehtinen B, et al.The importance of oxide morphology for the oxidation rate of zirconium alloys [A]. Zirconium in the Nuclear Industry: 11th International Symposium[C]. West Conshohocken, PA: ASTM International, 1996: 55 | [24] | Yao M Y, Wang J H, Peng J C, et al.Study on the role of second phase particles in hydrogen uptake behavior of zirconium alloys [A]. Zirconium in the Nuclear Industry: 16th International Symposium[C]. West Conshohocken, PA: ASTM International, 2011: 466 | [25] | Zhang W P, Yao M Y, Zhu L, et al.Corrosion behavior of Zr-0.8Sn-0.35Nb-0.4Fe-0.1Cr-xBi alloys in superheated steam at 400 ℃/10.3 MPa[J]. Corros. Prot., 2013, 34: 463 | [25] | (张伟鹏, 姚美意, 朱莉等. Zr-0.8Sn-0.35Nb-0.4Fe-0.1Cr-xBi合金在400 ℃过热蒸汽中的腐蚀行为[J]. 腐蚀与防护, 2013, 34: 463) | [26] | Yao M Y, Zhang Y, Li S L, et al.Effect of Cu content on the corrosion resistance of Zr-0.80Sn-0.34Nb-0.39Fe-0.10Cr-xCu alloy in superheated steam at 500 ℃[J]. Acta Metall. Sin., 2011, 47: 872 | [26] | (姚美意, 张宇, 李士炉等. Cu含量对Zr-0.80Sn-0.34Nb-0.39Fe-0.10Cr-xCu合金在500 ℃过热蒸汽中耐腐蚀性能的影响[J]. 金属学报, 2011, 47: 872) | [27] | Frankel P G, Wei J, Fruncis E M, et al.Effect of Sn on corrosion mechanisms in advanced Zr-cladding for pressurised water reactors [A]. Zirconium in the Nuclear Industry: 17th International Symposium[C]. West Conshohocken. PA: ASTM International, 2015: 404 | [28] | Platt P, Frankel P, Gass M, et al.Finite element analysis of the tetragonal to monoclinic phase transformation during oxidation of zirconium alloys[J]. J. Nucl. Mater., 2014, 454: 290 | [29] | Yan K P, Chen K M.The Processing Equipment Corrosion and Protection [M]. 2nd Ed., Beijing: Chemical Industry Press, 2009: 48 | [29] | (闫康平, 陈匡民. 过程装备腐蚀与防护 [M]. 第二版. 北京: 化学工业出版社, 2009: 48) | [30] | Zhang J L, Xie X F, Yao M Y, et al.Effect of Ge addition on corrosion performance of Zr-4 alloy in lithiated solution[J]. Chin. J. Nonferrous Met., 2013, 23: 1542 | [30] | (张金龙, 谢兴飞, 姚美意等. Ge含量对Zr-4合金在LiOH水溶液中耐腐蚀性能的影响[J]. 中国有色金属学报, 2013, 23: 1542) |
|
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
|
Shared |
|
|
|
|
|
Discussed |
|
|
|
|