采用静态高压釜腐蚀实验研究了Zr-0.80Sn-0.34Nb-0.39Fe-0.1Cr-xCu(x=0.05-0.5, 质量分数, %)合金在500 ℃, 10.3 MPa过热蒸汽中的耐腐蚀性能, 利用TEM观察了合金的显微组织. 结果表明: 添加(0.05-0.5)Cu对合金在500 ℃过热蒸汽中的耐腐蚀性能影响不大. 当x≦0.2时, 合金中的第二相主要为 hcp结构的Zr(Fe, Cr, Nb)2和含Cu的正交结构的Zr3Fe; 当x>0.2时, 除了Zr(Fe, Cr, Nb)2和含Cu的Zr3Fe外, 还有四方结构的Zr2Cu析出. Zr(Fe, Cr, Nb)2比较细小, 而含Cu第二相的尺寸较大. 即使在添加0.05Cu的合金中也有含Cu第二相析出, 说明Cu在该合金α-Zr基体中的固溶量很低. 因此, 添加(0.05-0.5)Cu对该合金在500 ℃过热蒸汽中的耐腐蚀性能影响不大的原因可能与固溶在α-Zr基体中的 Cu含量低有关.
姚美意
,
张宇
,
李士炉
,
张欣
,
周军
,
周邦新
. 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(7)
: 872
-876
.
DOI: 10.3724/SP.J.1037.2011.00236
The effect of Cu content on the corrosion resistance of Zr-0.8Sn-0.34Nb-0.39Fe-0.1Cr-xCu alloys (x=0.05-0.5, mass fraction, %) was investigated in superheated steam at 500 ℃ and10.3 MPa by autoclave tests. The microstructures of the alloys are observed by TEM. The results show that (0.05-0.5)Cu addition has little effect on the corrosion resistance of the alloys. When x is below 0.2, the precipitates Zr(Fe, Cr, Nb)2 with hcp structure and Zr3Fe containing Cu with orthorhombic structure are detected. When x is above 0.2, besides Zr(Fe, Cr, Nb)2 and Zr3Fe containing Cu, the precipitate of Zr2Cu with tetragonal structure is also detected. Zr(Fe, Cr, Nb)2 precipitates are smaller than the precipitates containing Cu in size. The precipitates containing Cu are found in the alloy even with 0.05Cu, indicating that the Cu content in α-Zr matrix is very small. Therefore, the reason that the Cu content has little effect on the corrosion resistance of the alloys is maybe related to the lower Cu content in α-Zr matrix.
[1] IAEA–TECDOC–996, IAEA, Vienna, 1998, ISSN 1011–4289, January, 1998
[2] Garzarolli F, Broy Y, Busch R A. In: Bradley E R, Sabol G P, eds., Zirconium in the Nuclear Industry: 11th International Symposium, ASTM STP 1295, Garmisch–Partenkirchen, Germany: ASTM International, 1996: 850
[3] Isobe T, Matsuo Y. In: Eucken C M, Garde A M, eds., Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, Philadelphia: ASTM International, 1991: 346
[4] Takeda K, Anada H. In: Sabol G P, Moan G D, eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohocken, PA: ASTM International, 2000: 592
[5] Broy Y, Garzarolli F, Seibold A, Van Swam L F. In: Sabol G P, Moan G D, eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohocken, PA: ASTM International, 2000: 609
[6] Yueh H K, Kesterson R L, Comstock R J, Shah H H, Colburn D J, Dahlback M, Hallstadius L. J ASTM Int, 2005; 2: 330
[7] Park J Y, Choi B K, Yoo S J, Jeong Y H. J Nucl Mater, 2006; 359: 59
[8] Jung Y H, Lee M H, Kim H G, Park J Y, Jeong Y H. J Alloys Compd, 2009; 479: 423
[9] Li S L, Yao M Y, Zhang X, Geng J Q, Peng J C, Zhou B X. Acta Metall Sin, 2011; 47: 163
(李士炉, 姚美意, 张欣, 耿建桥, 彭剑超, 周邦新. 金属学报, 2011; 47: 163)
[10] Hong H S, Moon J S, Kim S J, Lee K S. J Nucl Mater, 2001; 297: 113
[11] Mardon J P, Charquet D, Senevat J. In: Sabol G P, Moan G D, eds., Zirconium in the Nuclear Industry: Twelfth International Symposium, ASTM STP 1354, West Conshohocken,
PA: ASTM International, 2000: 505
[12] Yao M Y. PhD Thesis. Shanghai University, 2007
(姚美意. 上海大学博士论文, 2007)
[13] Jeong Y H, Lee K O, Kim H G. J Nucl Mater, 2002; 302: 9
[14] Kim H G, Jeong Y H, Kim T H. J Nucl Mater, 2004; 326: 125
[15] Jeong Y H, Kim H G, Kim D J. J Nucl Mater, 2003; 323: 72
[16] Yao M Y, Zhou B X, Li Q, Liu W Q, Geng X, Lu Y P. J Nucl Mater, 2008; 374: 197
