金属学报  2010, Vol. 46 Issue (10): 1258-1266    DOI: 10.3724/SP.J.1037.2010.00236

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镍基合金焊接过渡区微观结构及应力腐蚀行为研究

侯娟1,彭群家2,庄子哲雄2,王俭秋1,柯伟1,韩恩厚1

1. 中国科学院金属研究所 腐蚀与防护国家重点实验室, 沈阳 110016 2. 日本东北大学 断裂与可靠性研究中心, 仙台 980--8579

STUDY OF MICROSTRUCTURE AND STRESS CORROSION CRACKING BEHAVIOR IN WELDING TRANSITION ZONE OF Ni–BASED ALLOYS

HOU Juan 1, PENG Qunjia 2, SHOJI Testuo 2, WANG Jianqiu 1, KE Wei 1, HAN Enhou1

1. State Key Laboratory for Corrosion and Protection, Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016 2. Fracture and Reliability Research Institute, Tohoku University, Sendai 980–8579, Japan

侯娟 彭群家 庄子哲雄 王俭秋 柯伟 韩恩厚. 镍基合金焊接过渡区微观结构及应力腐蚀行为研究[J]. 金属学报, 2010, 46(10): 1258-1266.
, , , , , . STUDY OF MICROSTRUCTURE AND STRESS CORROSION CRACKING BEHAVIOR IN WELDING TRANSITION ZONE OF Ni–BASED ALLOYS[J]. Acta Metall Sin, 2010, 46(10): 1258-1266.

摘要 参考文献 相关文章 Metrics 全文: PDF(3469 KB)   摘要: 利用微观分析手段深入分析了镍基合金690-52同种金属焊接和镍基182合金-A533B低合金钢异种金属焊接的焊接过渡区微观结构, 定量测量了同种金属焊接热影响区(HAZ)残余应变分布, 用带缝隙的弯曲横梁样品模拟了异种金属焊接过渡区在高温含氧水中的应力腐蚀开裂(SCC)行为. 结果表明, 同种金属焊接过渡区的HAZ具有残余应变峰值、敏感的晶界微观结构, 因而导致最高的SCC敏感性; 异种金属焊接过渡区具有复杂的微观结构和成分分布, 典型特征是靠近熔接线(FB)的熔合区(FZ)内形成平行于FB的type-II和连接FB与type-II的type-I晶界,type-II具有高的SCC敏感性和裂纹扩展速率, type-I引导裂纹向FB扩展, 裂纹到达FB后发生点蚀钝化停止扩展, FB起阻碍裂纹进一步向低合金钢扩展的作用. 关键词 ： 镍基合金,  同种/异种金属焊接,  微观结构,  残余应变,  应力腐蚀开裂     Abstract：Welding technique is generally used in nuclear power plant for manufacturing and machining important components such as steam generator. The similar metal weld and dissimilar metal weld were commonly involved to connect and fixup tubings in steam generators. However, in recent years large amounts of cracking accidents have been observed in the welded joints. A concern has been raised about the integrity and reliability in the joint transition zone due to the high susceptibility of heat affected zone (HAZ) and fusion zone (FZ) to stress corrosion cracking (SCC). In this study, the similar metal and dissimilar metal joints were investigated and compared, focusing on the correlation between microstructure, residual strain and SCC behavior. The microstructures of transition zone in Ni–based Alloys 690 and 52 similar metal joint and Alloys 182 and A533B low alloy steel dissimilar metal joint were investigated comprehensively by SEM, EBSD, TEM. The residual strain distribution in the HAZ of 690–52 similar metal joint was quantitatively measured. The SCC behavior of 182–A533B dissimilar metal joint in high temperature oxygenated water were simulated by creviced bent beam specimen. The HAZ in the similar joint exhibits higher residual strain, sensitive microstructure and high susceptibility to SCC, therefoe, the HAZ region deserve more attention during the inspection and examination of components. The FZ othe dssimilar metal joint exhibits complicated microstructure and chemical composition. The type–II which parallels the fusion boundary (FB) and type–I linking the FB and type–II was typical in the FZ of the dissimilar weld. The SCC susceptibility and cracking growth rate are higher at type–II boundary in the FZ. The role of type–I boundary is to lead the crack growth to the FB. After reaching the FB, the crack growth is blunted by pitting. The FB plays a barrier role to the crack growth in the low alloy steel. The FZ in dissimilar metal joint is weak and high susceptible to SCC. Key words： Ni–based alloy    similar/dissimilar metal weld    microstructure    residual strain    stress corrosion cracking 收稿日期: 2010-05-18      基金资助: 国家重点基础研究发展计划(973)G2006CB605000 作者简介: 侯娟, 女, 1983年生, 博士生 服务 把本文推荐给朋友 加入引用管理器 E-mail Alert RSS 作者相关文章 侯娟 彭群家 庄子哲雄 王俭秋 柯伟 韩恩厚 44.8K 链接本文: https://www.ams.org.cn/CN/10.3724/SP.J.1037.2010.00236      或      https://www.ams.org.cn/CN/Y2010/V46/I10/1258 [1] Ding X S. Nucl Power Plants, 2003: 4; 11 (丁训慎. 核电站 2003: 4; 11) [2] Li B C, Dai B, Wang X Y. Modern Elec Power, 2004: 21; (李必成, 戴兵, 王先元. 现代电力, 2004: 21卷 02期) [3] Sireesha M, Albert S K, Shankar V, Sundaresan S. J Nucl Mater 2000: 279; 65 [4] Amzallag C, Boursier J M, Pages C, Gimond C. In: the 10th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems - Water Reactors, NACE, 2001 [5] Peng Q J, Shoji T, Yamauchi H, Takeda Y. Corros Sci 2007: 49; 2767 [6] Shoji T, Lu Z P, Yamazaki S. 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