Evaluation of Caustic Stress Corrosion Resistance of Steam Generator Tubing Alloy 690 for Nuclear Power Plant

被引:0
|
作者
Tang Zhanmei [1 ]
Meng Fanjiang [2 ]
Zhang Pingzhu [1 ]
Xu Xuelian [2 ]
Hu Shilin [1 ]
机构
[1] China Inst Atom Energy, Beijing 102413, Peoples R China
[2] Shanghai Nucl Engn Res & Design Inst, Shanghai 200233, Peoples R China
关键词
alloy; 690; C-ring specimen; caustic stress corrosion cracking; NaOH; CRACKING;
D O I
暂无
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
With the long term immersion test of C-ring specimens loaded by two levels of load value, the caustic stress corrosion cracking (caustic-SCC) resistance of three kinds of steam generator tubing alloy 690 in 50% NaOH at 325 degrees C was evaluated. The stress value after loading was measured by XRD and the oxide film after immersion was analyzed. The results show that: (1) The maximum stress value of C-ring specimens is released to a certain extent after loading slowly by screw, and the release amount of load value of the domestic tubes is larger than that of the imported tubes; (2) The domestic tubes and the imported tubes all have good caustic-SCC resistance in 50% NaOH medium at 325 degrees C, and the oxide film characteristics of the domestic tubing A are closer to those of the imported tubing C; (3) The good resistance of caustic stress corrosion of tubing alloy 690 in high concentrated alkaline medium at high temperature is related to the double-layer structured oxide film and the continuous carbide structure along grain boundary.
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页码:3541 / 3547
页数:7
相关论文
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