Study on stress corrosion cracking susceptibility of 316LN in simulated primary loop of PWR under abnormal water chemistry conditions

被引:0
|
作者
Tang, Zhan-Mei [1 ]
Hu, Shi-Lin [1 ]
Zhang, Ping-Zhu [1 ]
机构
[1] China Institute of Atomic Energy, P. O. Box 275-83, Beijing
来源
Yuanzineng Kexue Jishu/Atomic Energy Science and Technology | 2014年 / 48卷 / 11期
关键词
Chloride ion; Dissolved oxygen; SCC; SSRT method;
D O I
10.7538/yzk.2014.48.11.1960
中图分类号
学科分类号
摘要
It was studied that the effects of chloride ions and dissolved oxygen on stress corrosion cracking (SCC) behavior of 316LN stainless steel in simulated primary loop of pressure water reactor (PWR) under abnormal water chemistry conditions with slow strain rate test (SSRT) method. The results show that in saturated oxygen condition, the extension of specimens decreases gradually while the SCC sensitive index increases with the increase of chloride ions concentration. In addition, the samples will produce SCC in the case that the concentration of chloride ions is more than 1 mg/L. However, cracks are not initiated in de-aerated solution even if the concentration of chloride ions increases to 10 mg/L. The stress corrosion cracks of 316LN are initiated in defects or Cr-depleted zones at the surface and transgranularly propagates into the base metal. ©, 2014, Yuanzineng Kexue Jishu/Atomic Energy Science and Technology. All right reserved.
引用
收藏
页码:1960 / 1964
页数:4
相关论文
共 9 条
  • [1] Nordmann F., Overview of PWR water chemistry, International Seminar on Material and Water Chemistry in Nuclear Power Plants, pp. 1-15, (2007)
  • [2] Boursier J.M., Gallet S., Rouillon Y., Et al., Stress corrosion cracking of austenitic stainless steels in PWR primary water: An update of metallurgical investigations performed on french withdrawn components, Proceedings of Contribution of Materials Investigation to the Resolution of Problems Encountered in Pressurized Water Reactors, pp. 129-135, (2002)
  • [3] Tang Z., Hu S., Zhang P., Effect of chloride and oxygen on stress corrosion cracking of 304N in high temperature water, Atomic Energy Science and Technology, 46, 11, pp. 1296-1300, (2012)
  • [4] Tang Z., Hu S., Zhang P., Stress corrosion cracking of 316Ti in 300 ℃ high temperature water containing chloride ions, Journal of Chinese Society for Corrosion and Protection, 32, 4, pp. 291-295, (2012)
  • [5] Pan C., Li Z., Tian Z., Et al., Hydrogen embrittlement of weld metal of austenitic stainless steels, Acta Metallurgica Sinica, 37, 9, pp. 985-990, (2001)
  • [6] Szklarska-Smialowska Z., Mechanism of pit nucleation by electrical breakdown of the passive film, Corrosion Science, 44, pp. 1143-1149, (2002)
  • [7] Lv G., Xu C., Cheng H.-D., Et al., Critical chloride concentration of stress corrosion cracking for 304 stainless steel, Chemicl Industry and Engineering Progress, 27, 8, pp. 1284-1287, (2008)
  • [8] Shibata T., Passivity breakdown and stress corrosion cracking of stainless steel, Corrosion Science, 49, pp. 20-30, (2007)
  • [9] Peng Q.J., Li G.F., Shoji T., The crack tip solution chemistry in sensitized stainless steel in simulated boiling water reactor water studied using a micro-sampling technique, Journal of Nuclear Science and Technology, 40, 6, pp. 398-404, (2003)