Effect of thermal ageing on the corrosion behaviour of austenitic stainless steel welds in the simulated PWR primary water

被引：18
作者：
Chen, Junjie [1 ]
Jang, Changheui [1 ]
Kong, Byeon Seo [1 ]
Xiao, Qian [1 ]
Subramanian, Gokul Obulan [1 ]
Kim, Ho Sub [2 ]
Shin, Ji Ho [1 ]
机构：
[1] Korea Adv Inst Sci & Technol, Daejeon 34141, South Korea
[2] Def Agcy Technol & Qual, Jinju 52851, South Korea
来源：
CORROSION SCIENCE | 2020年 / 172卷
基金：
新加坡国家研究基金会;
关键词：
Thermal ageing; Stainless steel weld; Oxide structure; Ferrite; Austenite; OXIDE-FILM; CRACKING BEHAVIOR; POURBAIX DIAGRAMS; ATOM-PROBE; ALLOY; 690; TEMPERATURE; EMBRITTLEMENT; MICROSCOPY; TOUGHNESS; CHROMIUM;
D O I：
10.1016/j.corsci.2020.108730
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The corrosion behaviour of as-welded and thermally aged ER316L in simulated pressurised water reactor (PWR) primary water was studied. Significant spinodal decomposition without G-phase was observed after thermal ageing. Thermal ageing does not change the duplex oxide film formation mechanism on ER316L. Slightly higher Fe and Ni concentrations are in the external oxide particles of thermally aged ER316L. More Ni enrichment is in ferrite of as-welded ER316L beneath the ferrite/inner oxide layer interface. Oxide films of thermally aged ER316L show higher point defect densities and lower EIS resistances.
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页数：10
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