期刊文献+

Microstructure, Residual Strain and Stress Corrosion Cracking Behavior in 316L Heat-Affected Zone 被引量:3

Microstructure, Residual Strain and Stress Corrosion Cracking Behavior in 316L Heat-Affected Zone
原文传递
导出
摘要 Austenitic stainless steels are usually chosen to make many components of nuclear power plants (NPPs). However, their microstructure in the heat-affected zone (HAZ) will change during the welding process. Some failures of the weld joints, mainly stress corrosion cracking (SCC), have been found to be located in the HAZ. In this research, the microstructure, micro-hardness, residual strain and SCC behavior at different locations of the 316L HAZ cut from a safeend dissimilar metal weld joint were studied. However, traditional optical microscope observation could not find any microstructural difference between the HAZ and the base metal, higher residual strain and micro-hardness, and higher fraction of random high-angle grain boundaries were found in the HAZ than in the base metal when studied by using electron back-scattering diffraction scanning and micro-hardness test. What's more, the residual strain, the microhardness and the fraction of random grain boundaries decreased, while the fraction of coincidence site lattice grain boundaries increased with increasing the distance from the fusion boundary in 316L HAZ. Creviced bent beam test was applied to evaluate the SCC susceptibility at different locations of 316L HAZ and base metal. It was found that the HAZ had higher SCC susceptibility than the base metal and SCC resistance increased when increasing the distance from the fusion boundary in 316L HAZ. Austenitic stainless steels are usually chosen to make many components of nuclear power plants (NPPs). However, their microstructure in the heat-affected zone (HAZ) will change during the welding process. Some failures of the weld joints, mainly stress corrosion cracking (SCC), have been found to be located in the HAZ. In this research, the microstructure, micro-hardness, residual strain and SCC behavior at different locations of the 316L HAZ cut from a safeend dissimilar metal weld joint were studied. However, traditional optical microscope observation could not find any microstructural difference between the HAZ and the base metal, higher residual strain and micro-hardness, and higher fraction of random high-angle grain boundaries were found in the HAZ than in the base metal when studied by using electron back-scattering diffraction scanning and micro-hardness test. What's more, the residual strain, the microhardness and the fraction of random grain boundaries decreased, while the fraction of coincidence site lattice grain boundaries increased with increasing the distance from the fusion boundary in 316L HAZ. Creviced bent beam test was applied to evaluate the SCC susceptibility at different locations of 316L HAZ and base metal. It was found that the HAZ had higher SCC susceptibility than the base metal and SCC resistance increased when increasing the distance from the fusion boundary in 316L HAZ.
出处 《Acta Metallurgica Sinica(English Letters)》 SCIE EI CAS CSCD 2016年第9期848-858,共11页 金属学报(英文版)
基金 financially supported by the National Natural Science Foundation of China (No. 51301183) Science and Technology Commission of Shanghai Municipality under Grant No. 14DZ2250300, Shanghai, China
关键词 Austenitic stainless steels Heat.affected zone MICROSTRUCTURE EBSD Residual strain Stresscorrosion cracking Austenitic stainless steels Heat.affected zone Microstructure EBSD Residual strain Stresscorrosion cracking
  • 相关文献

参考文献35

  • 1H.T. Wang, G.Z. Wang, F.Z. Xuan, C.J. Liu, S.T. Tu, Mater. Sci. Eng. A Struct. 568, 108 (2013).
  • 2H. Ming, Z. Zhang, J. Wang, E.-H. Han, W. Ke, Mater. Charact. 97, 101 (2014).
  • 3J. Hou, T. Shoji, Z.P. Lu, Q.J. Peng, J.Q. Wang, E.H. Han, W. Ke, J. Nuc!. Mater. 397, 109 (2010).
  • 4S. Wang, J. Ding, H. Ming, Z. Zhang, J. Wang, Mater. Charact. 100, 50 (2015).
  • 5S. Suzuki, K. Takamori, K. Kumagayi, A. Sakashita, N. Yamashita, C. Shitara, Y. Okamura, E J. Adv. Maint. 1, 1 (2009).
  • 6H. Ming, R. Zhu, Z. Zhang, J. Wang, E.-H. Han, W. Ke, M. Su, Mater. Sci. Eng. A Struct. 669, 279 (2016).
  • 7Z.P. Lu, T. Shoji, Y. Takeda, Y. Ito, A. Kai, N. Tsuchiya, Corros. Sci. 50, 625 (2008).
  • 8Z.P. Lu, T. Shoji, S. Yamazaki, K. Ogawa, Corros. Sci. 58,211 (2012).
  • 9Z.P. Lu, T. Shoji, H. Xue, F.J. Meng, c.v, Fu, Y. Takeda, K. Negishi, J. Nuc!. Mater. 423, 28 (2012).
  • 10T.K. Yeh, G.R. Huang, M.Y. Wang, C.H. Tsai, Prog. Nuc!. Energy 63, 7 (2013).

同被引文献15

引证文献3

二级引证文献27

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部