贺韶,韩姚磊,李玉龙,明庭云,尚建路,汪家梅,梅金娜,朱平,张乐福,彭群家.注锌对316L不锈钢焊接接头应力腐蚀开裂行为影响研究[J].装备环境工程,2025,22(3):127-135. HE Shao,HAN Yaolei,LI Yulong,MING Tingyun,SHANG Jianlu,WANG Jiamei,MEI Jinna,ZHU ping,ZHANG Lefu,PENG Qunjia.Effect of Zinc Injection on Stress Corrosion Cracking Behavior of 316L Stainless Steel Welded Joint[J].Equipment Environmental Engineering,2025,22(3):127-135.
注锌对316L不锈钢焊接接头应力腐蚀开裂行为影响研究
Effect of Zinc Injection on Stress Corrosion Cracking Behavior of 316L Stainless Steel Welded Joint
投稿时间:2024-10-24  修订日期:2024-12-11
DOI:10.7643/issn.1672-9242.2025.03.015
中文关键词:  应力腐蚀开裂  裂纹萌生  裂纹扩展  焊接接头  注锌  高温高压水  核电站中图分类号:TG172 文献标志码:A 文章编号:1672-9242(2025)03-0127-09
英文关键词:stress corrosion cracking  crack initiation  crack propagation  welded joint  zinc injection  high temperature high pressure water  nuclear power plant
基金项目:中国广核集团科研项目(3100129119);姑苏创新创业领军人才专项(ZXL2017112)
作者单位
贺韶 中广核研究院有限公司,广东 深圳 518000 
韩姚磊 苏州热工研究院有限公司,江苏 苏州 215004 
李玉龙 中广核研究院有限公司,广东 深圳 518000 
明庭云 苏州热工研究院有限公司,江苏 苏州 215004 
尚建路 苏州热工研究院有限公司,江苏 苏州 215004 
汪家梅 上海交通大学 核科学与工程学院,上海 200240 
梅金娜 苏州热工研究院有限公司,江苏 苏州 215004 
朱平 苏州热工研究院有限公司,江苏 苏州 215004 
张乐福 上海交通大学 核科学与工程学院,上海 200240 
彭群家 苏州热工研究院有限公司,江苏 苏州 215004 
AuthorInstitution
HE Shao China Nuclear Power Technology Research Institute Co., Ltd., Guangdong Shenzhen 518000, China 
HAN Yaolei Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu Suzhou 215004, China 
LI Yulong China Nuclear Power Technology Research Institute Co., Ltd., Guangdong Shenzhen 518000, China 
MING Tingyun Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu Suzhou 215004, China 
SHANG Jianlu Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu Suzhou 215004, China 
WANG Jiamei School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China 
MEI Jinna Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu Suzhou 215004, China 
ZHU ping Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu Suzhou 215004, China 
ZHANG Lefu School of Nuclear Science and Engineering, Shanghai Jiao Tong University, Shanghai 200240, China 
PENG Qunjia Suzhou Nuclear Power Research Institute Co., Ltd., Jiangsu Suzhou 215004, China 
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中文摘要:
      目的 研究316L不锈钢焊接接头在不同注锌含量高温高压水中的应力腐蚀开裂(SCC)行为,为核电站注锌技术应用提供支撑。方法 利用慢应变速率拉伸试验研究不锈钢焊接接头的SCC裂纹萌生行为,利用直流电压降技术研究SCC裂纹扩展行为。通过扫描电子显微镜、能谱分析和电子背散射电子衍射技术研究焊接接头SCC裂纹萌生位置和扩展路径的微观组织结构特征。结果 SCC裂纹萌生试验结果表明,在高温高压水环境中,所有注锌浓度下,焊接接头的熔覆金属区裂纹最多,热影响区次之,融合线未开裂。裂纹扩展试验结果显示,注锌对不锈钢焊接接头熔覆金属区域和热影响区应力腐蚀裂纹扩展行为的影响不显著,裂纹扩展速率均低于8.0×10–8 mm/s(1.6 mm/a)。结论 316L不锈钢焊接接头在不同注锌浓度环境中的应力腐蚀开裂敏感性均较低。
英文摘要:
      The work aims to study the stress corrosion cracking (SCC) behavior of 316L stainless steel welded joints in high temperature and high pressure water with different Zn injection concentrations, to provide a technical support for Zn injection technology of nuclear power plants. The SCC initiation behavior of a stainless steel welded joint was studied by slow strain rate tensile tests. The SCC propagation behavior in the zinc injection water was compared according to the direct current potential drop (DCPD). Microstructure characteristics of SCC crack initiation locations and propagation paths of welded joints were observed and analyzed by scanning electron microscopy, energy spectrum analysis and electron backscatter diffraction. The SCC crack initiation test results showed that under all zinc injection concentrations in high temperature and high pressure water environments, the cladding metal zone had the most cracks, followed by the heat affected zone, and the fusion line was not cracked. The crack propagation test results showed that the effect of zinc injection on the SCC initiation behavior and propagation behavior of the stainless steel welded joint is insignificant. The crack propagation rate was lower than 8.0×10–8 mm/s (1.6 mm/a). In conclusion, 316L stainless steel welded joints have low stress corrosion cracking sensitivity in different zinc injection concentrations.
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