|
|
|
| EFFECT OF PRE-DEFORMATION ON GRAINS AND PRECIPITATES OF Zr-Sn-Nb ALLOY DURING AGING |
| CHAI Linjiang, LUAN Baifeng, CHEN Jianwei, QIU Risheng, LIU Qing |
| College of Materials Science and Engineering, Chongqing University, Chongqing 400044 |
|
Cite this article:
CHAI Linjiang LUAN Baifeng CHEN Jianwei QIU Risheng LIU Qing. EFFECT OF PRE-DEFORMATION ON GRAINS AND PRECIPITATES OF Zr-Sn-Nb ALLOY DURING AGING. Acta Metall Sin, 2012, 48(1): 107-114.
|
|
|
Abstract Zirconium-based alloys are being used as fuel cladding and structural materials for nuclear reactors since they have a good irradiation stability, corrosion resistance and acceptable mechanical properties in a reactor environment. Recently, more advanced zirconium-based alloys are required for enhanced operating conditions such as an increased burn-up and higher operation temperatures. Therefore, the development of advanced zirconium alloys for a fuel cladding is being progressed in various countries. Among the developed new zirconium alloys, a low Nb containing alloy series designed by China is a group of promising cladding material. For the new alloy system, optimum manufacturing processes are significant factors to improve properties and need urgently to be established. In this work, electron channeling contrast (ECC), secondary electron (SE) imaging and energy dispersive spectroscopy (EDS) analyzing techniques are employed to investigate the effect of pre-deformation following β-quenching on recrystallization and precipitating behavior of a new Zr-Sn-Nb alloy during aging. The results show that remarkable differences exist between the microstructure of specimens with and without pre-deformation prior to aging at the same temperature (650 ℃). Specimens aged without pre-deformation present extremely heterogeneous recrystallized grains that generally own irregular shape. The size discrepancy between the intragranularly fine Zr(Fe, Cr, Nb)2 precipitates and the larger ones, which is Cu-containing Zr3Fe particles and distribute along the conserved prior $\beta$ grain boundaries, are distinct. While for specimens aged following 20% pre-deformation, the recrystallized α-grains are evidently fined and homogenized. The size discrepancy between the two sorts of precipitates decrease as well and the larger ones change to distribute along recrystallized α-grain boundaries. Therefore, the introduction of pre-deformation is able to change markedly the characteristics of microstructure and second phase particles distribution and further be utilized to obtain preferred microstructure.
|
|
Received: 23 August 2011
|
|
|
| Fund: Supported by New Century Excellent Talents in University (No.NCET-08-0606), Fundamental Research Funds for the Central Universities
(Nos.CDJZR10130008 and CDJXS10132201) |
| [1] Thorvaldsson T, Andersson T, Wilson A, Wardle A. In: Van Swam L F P, Eucken C M eds., Zirconium in the Nuclear Industry: 8th International Symposium, ASTM STP 1023, Philadelphia: ASTM International, 1989: 128[2] Garzarolli F, Steinberg E, Weidinger H G. In: Van Swam L F P, Eucken C M eds., Zirconium in the Nuclear Industry:8th International Symposium, ASTM STP 1023, Philadelphia: ASTM International, 1989: 202[3] Foster J P, Dougherty J, Burke M G, Bates J F, Worcester S. J Nucl Mater, 1990; 173: 164[4] Garzarolli F, Stehle H, Steinberg E. In: Bradley E R, Sabol G P eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, West Conshohocken: ASTM International, 1996: 12[5] Gros J P, Wadier J F. J Nucl Mater, 1990; 172: 85[6] Zhou B X, Yang X L. Nucl Power Eng, 1997; 18: 511(周邦新, 杨晓林. 核动力工程, 1997; 18: 511)[7] Comstock R J, Schoenberger G, Sabol G P. In: Bradley E R, Sabol G P eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, West Conshohocken: ASTM International, 1996: 710[8] Nikulina A V, Markelov V A, Peregud M M, Bibilashvili Y, Kotrekhov V A, Lositsky A F, Kuzmenko N V, Shevnin Y P, Shamardin V K, Kobylyansky G P, Novoselov A E. In:Bradley E R, Sabol G P eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295,West Conshohocken: ASTM International, 1996: 785[9] Jeong Y H, Park S Y, Lee M H, Choi B K, Baek J Y, Park J Y, Kim J H, Kim H G. J Nucl Sci Technol, 2006; 43: 977[10] Zhao W J. Rare Met Lett, 2004; 23: 15(赵文金. 稀有金属快报, 2004; 23: 15)[11] Li Z K, Zhou L, Zhang J J, Wang W S, Jin Z H. Rare Met Mater Eng, 2004; 33: 1362(李中奎, 周廉, 张建军, 王文生, 金志浩. 稀有金属材料与工程, 2004; 33: 1362)[12] Yan Q S, Liu W Q, Lei M, Li Q, Yao M Y, Zhou B X. Rare Met Mater Eng, 2007; 36: 104(严青松, 刘文庆, 雷鸣, 李强, 姚美意, 周邦新. 稀有金属材料与工程, 2007; 36: 104)[13] Guo X C, Luan B F, Chen J W, Zhou J, Zhang X Y, Li Z K, Liu Q. Rare Met Mater Eng, 2011; 5: 813(过锡川, 栾佰峰, 陈建伟, 周军, 张喜燕, 李中奎, 刘 \ \ 庆. 稀有金属材料与工程, 2011; 5: 813)[14] Waterloo G, Hansen V, Gjφnnes J, Skjervold S R. Mater Sci Eng, 2001; A303: 226[15] Deschamps A, Livet F, Br´echet Y. Acta Mater, 1998; 47: 281[16] Liu P, Kang B X, Cao X G, Huang J L, Yen B, Gu H C. Mater Sci Eng, 1999; A265: 262[17] Song Z Y, Sun Q Y, Xiao L, Sun J, Ge P. Rare Met Mater Eng, 2010; 39: 791(宋振亚, 孙巧艳, 肖 林, 孙 军, 葛鹏. 稀有金属材料与工程, 2010; 39: 791)[18] Yuan Z X, Song S H, Wang Y H, Liu J, Guo A M. Mater Lett, 2005; 59: 2048[19] Kim J M, Jeong Y H. J Nucl Mater, 1999; 275: 74[20] Xue X Y, Song Q Z, Liu J Z, Li P Z. Rare Met Mater Eng, 1998; 27: 302(薛祥义, 宋启忠, 刘建章, 李佩志. 稀有金属材料与工程, 1998; 27: 302)[21] Liu P, Ornhagen C, Nilsson J O. Scr Mater, 1998; 38: 775.[22] Holt R A. J Nucl Mater, 1970; 35: 322[23] Okvist G, K¨allstr¨om K. J Nucl Mater, 1970; 35: 316[24] Woo O T, Tangri K. J Nucl Mater, 1979; 79: 82[25] Jeong Y H, Rheem K S, Choi C S, Kim Y S. J Nucl Sci Technol, 1993; 30: 154[26] Hong H S, Kim S J, Lee K S. J Nucl Mater, 1999; 265:108[27] Yao M Y, Zhang Y, Li S L, Zhang X, Zhou J, Zhou B X. Acta Metall Sin, 2011; 47: 872(姚美意, 张宇, 李士炉, 张 欣, 周军, 周邦新. 金属学报, 2011; 47: 872)[28] Garzarolli F, Goll W, Seibold A, Ray I. In: Bradley E R, Sabol G P eds., Zirconium in the Nuclear Industry: 11thInternational Symposium, ASTM STP 1295, West Conshohocken: ASTM International, 1996: 541[29] Ruhmann H, Manzel R, Sell H, Charquet D. In: Bradley E R, Sabol G P eds., Zirconium in the Nuclear Industry:11th International Symposium, ASTM STP 1295, West Conshohocken: ASTM International, 1996: 865[30] Eucken C, Finden E T, Trapp–Pritsching S, Weidinger H G. In: Van Swam L F P, Eucken C M eds., Zirconium in the Nuclear Industry: 8th International Symposium,ASTM STP 1023, Philadelphia: ASTM International, 1989: 113[31] Pan J S, Tong J M, Tian M B. The Fundamental of Materials Science. Beijing: Tsinghua Unviersity Press, 1998: 567(潘金生, 仝健民, 田民波. 材料科学基础. 北京: 清华大学出版社, 1998: 567)[32] Loucif K, Borrelly R, Merle P. J Nucl Mater, 1994; 210: 84[33] Maussner G, Steinberg E, Tenckhoff E. In: Van Swam L F P, Adamson R B eds., Zirconium in the Nuclear Industry: 7th International Symposium, ASTM STP 939, Philadelphia:ASTM International, 1987: 307[34] Rollett A D, Srolovitz D J, Doherty R D, Anderson M P. Acta Metall, 1989; 37: 627[35] Humphreys F J, Hatherly M. Recrystallisation and Related Annealing Phenomena. 2nd Ed., Oxford: Elsevier Ltd, 2004: 109 |
| No Suggested Reading articles found! |
|
|
Viewed |
|
|
|
Full text
|
|
|
|
|
Abstract
|
|
|
|
|
Cited |
|
|
|
|
| |
Shared |
|
|
|
|
| |
Discussed |
|
|
|
|
