Microstructure and stress corrosion cracking of a SA508-309L/308L-316L dissimilar metal weld joint in primary pressurized water reactor environment

被引:37
|
作者
Dong, Lijin [1 ,2 ]
Ma, Cheng [1 ]
Peng, Qunjia [1 ]
Han, En-Hou [1 ]
Ke, Wei [1 ]
机构
[1] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
[2] Southwest Petr Univ, Sch Mat & Engn, Chengdu 610500, Peoples R China
基金
中国国家自然科学基金;
关键词
Dissimilar metal weld joint; Stress corrosion cracking; Microstructure; Primary pressurized water reactor environment; Slow strain rate tension; LOW-ALLOY STEEL; AUSTENITIC STAINLESS-STEELS; HEAT-AFFECTED ZONE; FUSION BOUNDARY REGION; BEHAVIOR; TRANSITION; SUSCEPTIBILITY; CHEMISTRY;
D O I
10.1016/j.jmst.2019.08.035
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Stress corrosion cracking (SCC) of an SA508-309 L/308 L-316 L dissimilar metal weld joint in primary pressurized water reactor environment was investigated by the interrupted slow strain rate tension tests following a microstructure characterization. The 308 L weld metal shows a higher content of delta ferrite than the 309 L weld metal. In addition, no obvious Cr-depletion but carbides precipitation at gamma/delta phase boundaries was observed in both 308 L and 309 L weld metals. The slow strain rate tension tests showed that the SCC susceptibility of the base and weld metals of the dissimilar metal weld joint follows the order of SA508 < 308 L weld metal < the heat affected zone of 316 L base metal < 309 L weld metal. The higher SCC susceptibility of 309 L weld metal than that of 308 L weld metal is likely due to the lower content of 8 ferrite. In addition, a preferential SCC initiation in the 309 L weld metal adjacent to 308 L weld metal is attributed to few carbides in this region. (C) 2019 Published by Elsevier Ltd on behalf of The editorial office of Journal of Materials Science & Technology.
引用
收藏
页码:1 / 14
页数:14
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