|
|
|
| STUDY OF ANISOTROPIC BEHAVIOR FOR ZIRCONIUM ALLOYS CORRODED IN LITHIATED WATER |
| SUN Guocheng1, 2), ZHOU Bangxin1, 2), YAO Meiyi1, 2), XIE Shijing1, 2), LI Qiang 1, 2) |
1) Laboratory for Microstructures, Shanghai University, Shanghai 200444
2) Institute of Materials, Shanghai University, Shanghai 200072 |
|
Cite this article:
SUN Guocheng ZHOU Bangxin YAO Meiyi XIE Shijing LI Qiang . STUDY OF ANISOTROPIC BEHAVIOR FOR ZIRCONIUM ALLOYS CORRODED IN LITHIATED WATER. Acta Metall Sin, 2012, 48(9): 1103-1108.
|
|
|
Abstract Zirconium alloys of a hexagonal close--packed crystal structure have prominent anisotropic characteristic in comparison with metals of a cubic crystal structure and a strong texture is produced in sheet or tubular materials during the fabrication process. The anisotropic characteristic is bound to be reflected on the corrosion behavior of zirconium alloys. In order to investigate the effect of texture and compositions on the anisotropic growth of oxide layer formed on zirconium alloys and clarify the mechanism of improving corrosion resistance by adding Nb in zirconium alloys, Zr-4, N18 and ZIRLO zirconium alloys with different contents of Nb were adopted as the experimental materials. All the plate specimens of zirconium alloys 2 mm in thickness have a similar texture. Corrosion tests were carried out in a static autoclave at 360 ℃, 18.6 MPa in lithiated water with 0.01 mol/L LiOH. The results show that the anisotropic growth of oxide layer on different surfaces of the specimens was only observed for Zr-4 specimen but not for N18 and ZIRLO specimens. The thickness of oxide layer develops much faster on the rolling surface (SN surface) than that on the surface perpendicular to the rolling direction (SR surface) and the surface perpendicular to the transversal direction (ST surface) for Zr-4 specimen after 90-100 d exposure, and the corrosion resistance on the SR and ST surfaces was much better than that on the SN surface. However, for N18 and ZIRLO specimens the anisotropic growth of oxide layer was restrained by the addition of Nb, and the oxide thickness on these three different surfaces was the same after 280 d exposure. Therefore the corrosion resistance of N18 and ZIRLO sheet or tubular specimens was superior to Zr-4 corroded in lithiated water, because the oxide layers grew mainly on the SN surface of the specimens. If making a comparison among Zr-4, N18 and ZIRLO specimens about the growth rate of oxide layers only on the SR and ST surfaces, it is shown that the growth rate of oxide layers increased with the increase of Nb content in these alloys. From a point of view for the improving corrosion resistance, the addition of Nb no more than 0.3\% (mass fraction) is recommended.
|
|
Received: 06 June 2012
|
| Fund: Supported by National Natural Science Foundation of China (No.50971084) |
| [1] Garzarolli F, Seidel H, Tricot R, Gros J P. In: Eucken C M, Garde A M eds., Zirconium in the Nuclear Industry: 9th International Symposium, ASTM STP 1132, Baltimore: ASTM International, 1991: 395[2] Yilmazbayhan A, Breval E, Motta A T, Comstock R J. J Nucl Mater, 2006; 349: 265[3] Zhou B X, Li Q, Yao M Y, Liu W Q, Chu Y L. In: Kammenzind B, Limb¨ack M eds., Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505, Baltimore: ASTM International, 2009: 360[4] Park J Y, Choi B K, Yoo S J, Jeong Y H. In: Kammenzind B, Limb¨ack M eds., Zirconium in the Nuclear Industry: 15th International Symposium, ASTM STP 1505, Baltimore: ASTM International, 2009: 471[5] Kim H G, Kim T H, Jeong Y H. J Nucl Mater, 2002; 306: 44[6] Zhou B X, Peng J C, Yao M Y, Li Q, Xia S, Du C X, Xu G. In: Limb¨ack M, Barb´eris P eds., Zirconium in the Nuclear Industry: 16th International Symposium, ASTM STP 1529, Bridgeport: ASTM International, 2011: 620[7] Charquet D, Tricot R, Wadier J E. In: Van Swam L F P, Eucken C M eds., Zirconium in the Nuclear Industry: 8th International Symposium, ASTM STP 1023, Baltimore: ASTM International, 1989: 374[8] Wang C T, Eucken C M, Graham R A. In: Eucken C M, Garde A M eds., Zirconium in the Nuclear Industry: 9th International Symposium, ASTM STP 1132, Baltimore: ASTM International, 1991: 319[9] Kearns J J. Report No.WAPD–TM–472, Report of Westinghouse Electric Corporation, Bettis Atomic Power Laboratory, Pittsburgh, PA, 1965: 2[10] Han J H, Rheem K S. J Nucl Mater, 1994; 217: 197[11] Pecheur D, Godlewski J, Billot P, Thomazet J. In: Sabol G P, Bradley E R eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, Ann Arbor: ASTM International, 1996: 94[12] Sabol G P, Kilp G R, Balfour M G, Roberts E. In: Van Swam L F P, Eucken C M eds., Zirconium in the Nuclear Industry: 8th International Symposium, ASTM STP 1023, Baltimore: ASTM International, 1989: 227[13] Nikulina A V, Markelov V A, Peregud M M, Bibilashvili Y K, Kotrekhov V A, Lositsky A F, Kuzmenko N V, Shevnin YP, ShamardinVK, KobylyanskyGP, NovoselovAE. In:Sabol G P, Bradley E R eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, Ann Arbor: ASTM International, 1996: 785[14] Zhou B X, Li Q, Huang Q, Miao Z, Zhao W J, Li C. Nucl Power Eng, 2000; 21: 439(周邦新, 李强, 黄强, 苗 志, 赵文金, 李聪. 核动力工程, 2000; 21: 439)[15] Zhou B X, Yao M Y, Li Z K,Wang X M, Zhou J, Long C S, Liu Q, Luan B F. J Mater Sci Technol, 2012; 28: 606[16] Zhou B X, Li Q, YaoMY, LiuWQ, Chu Y L. Nucl Power Eng, 2005; 26: 364(周邦新, 李强, 黄 强, 苗 志, 赵文金, 李 聪. 核动力工程, 2000; 21: 439)[17] Zhou B X, Li Q, Yao M Y, Liu W Q, Chu Y L. Corros Prot, 2009; 30: 589(周邦新, 李强, 姚美意, 刘文庆, 褚于良. 腐蚀与防护, 2009; 30: 589)[18] Du C X, Peng J C, Li H, Zhou B X. Acta Metall Sin, 2011; 47: 887(杜晨曦, 彭剑超, 李慧, 周邦新. 金属学报, 2011; 47: 887)[19] Geng J Q, Zhou B X, Yao M Y, Wang J H, Zhang X, Li S L, Du C X. J Shanghai Univ (Nat Sci Ed), 2011; 17: 293(耿建桥, 周邦新, 姚美意, 王锦红, 张欣, 李士炉, 杜晨曦. 上海大学学报(自然科学版), 2011; 17: 293)[20] Cox B. J Nucl Mater, 2005; 336: 331[21] Liu W Q, Zhou B X, Li Q. Nucl Power Eng, 2002; 23: 68(刘文庆, 周邦新, 李强. 核动力工程, 2002; 23: 68)[22] Zhou B X, Yao M Y, Li Q, Xia S, Liu W Q, Chu Y L. Rare Met Mater Eng, 2007; 36: 1317(周邦新, 姚美意, 李强, 夏爽, 刘文庆, 褚于良. 稀有金属材料与工程, 2007; 36: 1317) |
| No Suggested Reading articles found! |
|
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
| |
Shared |
|
|
|
|
| |
Discussed |
|
|
|
|
