铅对划伤690合金应力腐蚀行为的影响
Effect of Lead on Stress Corrosion Cracking Behavior for Scratched Alloy 690
摘 要
采用扫描电镜(SEM),背散射电子衍射(EBSD)和透射电镜(TEM)研究了划伤690合金在330 ℃含铅碱溶液和高纯水中的应力腐蚀开裂(SCC)行为。结果表明：划伤过程使690合金局部产生严重变形区，该区域初始晶粒出现细化；在330 ℃含铅碱溶液中浸泡后试样划伤侧边出现沿机械孪晶界生长的应力腐蚀裂纹束；在高温高纯水中持续浸泡后，已有裂纹仍快速向基体延伸。材料表面或裂纹路径残留的微量铅仍促进SCC裂纹或裂纹束持续快速生长。
划伤
铅
应力腐蚀开裂
alloy 690
scratch
lead
stress corrosion cracking (SCC)
Abstract
SEM, EBSD and TEM were used to study the stress corrosion cracking (SCC) behavior of scratched alloy 690 sample in lead-contaminated caustic solution and high purity water at 330 ℃. The results showed that highly deformed zone was produced during the scratching process, and original grains around the scratch groove were refined. A bundle of SCC cracks grew along mechanical twin boundaries after immersing in lead-contaminated caustic solution and the cracks continuously extended after continuing immersion in high purity water. A trace amount of residual lead on the surface of alloy 690 or crack path could advance crack growth.
中图分类号 TG174 DOI 10.11973/fsyfh-201609010
所属栏目 核电设备材料防护
基金项目 大型先进压水堆核电重大专项（2010ZX06004-018）
收稿日期 2015/7/3
修改稿日期
网络出版日期
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备注孟凡江(1982-)，高级工程师，博士，从事核电材料腐蚀与防护研究。
引用该论文: MENG Fan-jiang,ZHANG Zhi-ming,XU Xue-lian,WANG Jian-qiu,LIU Xiao-qiang. Effect of Lead on Stress Corrosion Cracking Behavior for Scratched Alloy 690[J]. Corrosion & Protection, 2016, 37(9): 735
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参考文献
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【3】STAEHLE R W, GORMAN J A. Quantitative assessment of submodes of stress corrosion cracking on the secondary side of steam generator tubing in pressurized water reactors: part 1[J]. Corrosion, 2003, 59: 932-994.
【4】MENG F J, WANG J Q, HAN E H, et al. Effects of scratching on corrosion and stress corrosion cracking of alloy 690TT at 58 ℃ and 330 ℃[J]. Corrosion Science, 2009, 51: 2761-2769.
【5】TKAYA M B, ZIDI M, MEZLINI S, et al. Influence of the attack angle on the scratch testing of an aluminum alloy by cones: experimental and numerical studies[J]. Materials and Design, 2008, 29: 98-104.
【6】MENG F J, HAN E H, WANG J Q, et al. Localized corrosion behavior of scratches on nickel-base alloy 690TT[J]. Electrochimica Acta, 2011, 56: 1781-1785.
【7】MENG F J, WANG J Q, HAN E H, et al. Microstructure near scratch on alloy 690TT and stress corrosion induced by scratching[J]. Acta Metallurgica Sinica, 2011, 47: 839-846.
【8】HLIE M, LARNBERT I, SANTARINI G. Some considerations about the possible mechanisms of lead assisted stress corrosion cracking of steam generator tubing[C]//7th International Symposium on Environmental Degradation of Materials in Nuclear Power System-water Reactors.[s.l.]:[s.n.], 1995: 247.
【9】HWANG S S, KIM H P, LEE D H, et al. Corrosion behavior of Ni-based alloys in lead contaminated water[C]//Proc. Int. Symp. Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors.[s.l.]:[s.n.], 1998: 403.
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