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Cyclic EIS investigation on corrosion evolution of 304 SS in simulated secondary circuit water of PWR system 期刊论文
ANTI-CORROSION METHODS AND MATERIALS, 2025, 卷号: 72, 期号: 1, 页码: 146-158
作者:  Ji, Yuefei;  Hao, Long;  Wang, Jianqiu;  Ke, Wei
收藏  |  浏览/下载：1/0  |  提交时间：2025/04/27
High-temperature and high-pressure water  Nuclear material  304 stainless steel  Corrosion evolution  Electrochemical impedance spectroscopy  Cyclic EIS  
Cyclic EIS investigation on corrosion evolution of 304 SS in simulated secondary circuit water of PWR system 期刊论文
ANTI-CORROSION METHODS AND MATERIALS, 2025, 卷号: 72, 期号: 1, 页码: 146-158
作者:  Ji, Yuefei;  Hao, Long;  Wang, Jianqiu;  Ke, Wei
收藏  |  浏览/下载：3/0  |  提交时间：2025/04/27
High-temperature and high-pressure water  Nuclear material  304 stainless steel  Corrosion evolution  Electrochemical impedance spectroscopy  Cyclic EIS  
Editorial: Nuclear materials degradation 期刊论文
FRONTIERS IN MATERIALS, 2023, 卷号: 10, 页码: 2
作者:  Ming, Hongliang;  Zhang, Zhiming;  Chen, Jian;  Noel, James J.
收藏  |  浏览/下载：7/0  |  提交时间：2024/01/07
nuclear material  corrosion  stress corrosion cracking  irradiation  materials for advanced  reactors  
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  
Evaluation of Fatigue Properties of CA6NM Martensite Stainless Steel Using Miniature Specimens 期刊论文
ACTA METALLURGICA SINICA, 2018, 卷号: 54, 期号: 10, 页码: 1359-1367
作者:  Ma Yefei;  Song Zhuman;  Zhang Siqian;  Chen Lijia;  Zhang Guangping
收藏  |  浏览/下载：125/0  |  提交时间：2021/02/02
martensite stainless steel  fatigue property  miniature specimen  size effect  nuclear power material  
EFFECTS OF FORGING AND HEAT TREATMENTS ON STRESS CORROSION BEHAVIOR OF 316LN STAINLESS STEEL IN HIGH TEMPERATURE CAUSTIC SOLUTION 期刊论文
ACTA METALLURGICA SINICA, 2015, 卷号: 51, 期号: 6, 页码: 659-667
作者:  Guo Yueling;  Han En-Hou;  Wang Jianqiu
收藏  |  浏览/下载：177/0  |  提交时间：2021/02/02
stainless steel  nuclear material  stress corrosion cracking  high temperature caustic solution  fractography  
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