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Effect of Surface State on Corrosion and Stress Corrosion for Nuclear Materials 期刊论文
ACTA METALLURGICA SINICA, 2023, 卷号: 59, 期号: 4, 页码: 513-522
作者:  Han En-Hou;  Wang Jianqiu
收藏  |  浏览/下载：7/0  |  提交时间：2024/01/07
surface state  corrosion  stress corrosion  irradiation-assisted stress corrosion  nuclear material  stainless steel  nickel-based alloy  
Life Prediction for Stress Corrosion Behavior of 316L Stainless Steel Elbow of Nuclear Power Plant 期刊论文
ACTA METALLURGICA SINICA, 2017, 卷号: 53, 期号: 4, 页码: 455-464
作者:  Guo Shu;  Han En-Hou;  Wang Haitao;  Zhang Zhiming;  Wang Jianqiu
收藏  |  浏览/下载：116/0  |  提交时间：2021/02/02
316L stainless steel elbow  stress corrosion crack propagation  crack opening displacement  finite element analysis  stress relaxation  cold work deformation  
Influence of temperature on electrochemical behavior and oxide film property of Alloy 800 in hydrogenated high temperature water 期刊论文
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2016, 卷号: 67, 期号: 8, 页码: 796-803
作者:  Wang, J. -Z.;  Wang, J. -Q.;  Han, E. -H.
收藏  |  浏览/下载：69/0  |  提交时间：2021/02/02
CORROSION BEHAVIOR OF ALLOY 800 IN NaOH AND ETA SOLUTIONS AT 300 degrees C 期刊论文
ACTA METALLURGICA SINICA, 2016, 卷号: 52, 期号: 5, 页码: 599-606
作者:  Wang Jiazhen;  Wang Jianqiu;  Han En-Hou
收藏  |  浏览/下载：117/0  |  提交时间：2021/02/02
alloy 800  ethanolamine  potentiodynanic polarization curve  oxide film  
CORROSION BEHAVIOR OF ALLOY 800 IN NaOH AND ETA SOLUTIONS AT 300 degrees C 期刊论文
ACTA METALLURGICA SINICA, 2016, 卷号: 52, 期号: 5, 页码: 599-606
作者:  Wang Jiazhen;  Wang Jianqiu;  Han En-Hou
收藏  |  浏览/下载：116/0  |  提交时间：2021/02/02
alloy 800  ethanolamine  potentiodynanic polarization curve  oxide film  
RESEARCH TRENDS ON MICRO AND NANO-SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT 期刊论文
ACTA METALLURGICA SINICA, 2011, 卷号: 47, 期号: 7, 页码: 769-776
作者:  Han En-Hou
收藏  |  浏览/下载：88/0  |  提交时间：2021/02/02
key material in nuclear power plant  stainless steel  nickel-based alloy  low alloy steel  zirconium alloy  corrosion  stress corrosion cracking  corrosion fatigue  flow assisted corrosion  irradiation degradation