Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment

被引：45
作者：
Dong, Lijin [1 ,2 ]
Peng, Qunjia [1 ]
Xue, He [3 ]
Han, En-Hou [1 ]
Ke, Wei [1 ]
Wang, Lei [2 ]
机构：
[1] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China
[2] Northeastern Univ, Minist Educ, Key Lab Anisotropy & Texture Mat, Shenyang 110819, Liaoning, Peoples R China
[3] Xian Univ Sci & Technol, Sch Mech Engn, Xian 710054, Shaanxi, Peoples R China
来源：
CORROSION SCIENCE | 2018年 / 132卷
基金：
中国国家自然科学基金;
关键词：
Nickel; Low alloy steel; SEM; TEM; Stress corrosion; Welding; LOW-ALLOY STEEL; HIGH-TEMPERATURE WATER; HEAT-AFFECTED ZONE; BWR COOLANT ENVIRONMENTS; GRAIN-BOUNDARY; METAL WELD; ASSISTED CRACKING; STAINLESS-STEEL; CHROMIUM DEPLETION; RESIDUAL-STRESS;
D O I：
10.1016/j.corsci.2017.12.011
中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
Correlation of microstructure and stress corrosion cracking (SCC) initiation behaviour of the fusion boundary (FB) region in a SA508 Cl. 3-Alloy 52M weld joint in primary pressurized water reactor environment was investigated. Cr-depletion at the grain boundary and strength mismatch in the FB region are the two causes for SCC initiation in the FB region. The partially mixed zone between the dilution zone (DZ) of Alloy 52M and SA508 Cl. 3 has a retardation effect on SCC initiation. This is attributed to the decrease of strength mismatch and the alleviation of strain concentration adjacent to the grain boundary in DZ.
引用
收藏
页码：9 / 20
页数：12
相关论文
共 57 条
[1]  
Alexandreanu B, 2011, 15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, P179
[2]  
Alexandreanu B, 2011, 15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, P245
[3]   Emerging issues and fundamental processes in environmental cracking in hot water (Reprinted from Proceedings of the CORROSION/2007 research topical symposium "Advances in Environmentally Assisted Cracking", 2007) [J].
Andresen, P. L. .
CORROSION, 2008, 64 (05) :439-464
[4]  
Andresen P. L., 2011, P 15 C ENV DEGR MAT, P267
[5]  
Andresen PL, 2011, 15TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS-WATER REACTORS, P161
[6]   Stress Corrosion Cracking of Current Structural Materials in Commercial Nuclear Power Plants [J].
Andresen, Peter L. .
CORROSION, 2013, 69 (10)
[7]  
[Anonymous], 2016, E8E8M16A ASTM INT
[8]  
Attanasio S.A., 2003, 11th International Conference on Environmental Degradation of Materials in Nuclear Power System - Water Reactors, ANS, P143
[9]  
Bai J.X., 2017, CORROS SCI
[10]   Microstructural and hardness investigations on a dissimilar metal weld between low alloy steel and Alloy 82 weld metal [J].
Chen, Z. R. ;
Lu, Y. H. ;
Ding, X. F. ;
Shoji, T. .
MATERIALS CHARACTERIZATION, 2016, 121 :166-174
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