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Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10
作者:  Tan, Jibo;  Zhang, Ziyu;  Zheng, Hui;  Wang, Xiang;  Gao, Jun;  Wu, Xinqiang;  Han, En-Hou;  Yang, Shuangliang;  Huang, Pengtao
收藏  |  浏览/下载：169/0  |  提交时间：2021/02/02
Corrosion fatigue  Austenitic stainless steel  High temperature corrosion  Model  
Corrosion fatigue model of austenitic stainless steels used in pressurized water reactor nuclear power plants 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2020, 卷号: 541, 页码: 10
作者:  Tan, Jibo;  Zhang, Ziyu;  Zheng, Hui;  Wang, Xiang;  Gao, Jun;  Wu, Xinqiang;  Han, En-Hou;  Yang, Shuangliang;  Huang, Pengtao
收藏  |  浏览/下载：167/0  |  提交时间：2021/02/02
Corrosion fatigue  Austenitic stainless steel  High temperature corrosion  Model  
Electrochemistry and In Situ Scratch Behavior of 690 Alloy in Simulated Nuclear Power High Temperature High Pressure Water 期刊论文
ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 11, 页码: 1474-1484
作者:  Li Xiaohui;  Wang Jianqiu;  Han En-Hou;  Guo Yanjun;  Zheng Hui;  Yang Shuangliang
收藏  |  浏览/下载：164/0  |  提交时间：2021/02/02
alloy 690  high temperature high pressure water  corrosion  in situ scratch  
Electrochemistry and In Situ Scratch Behavior of 690 Alloy in Simulated Nuclear Power High Temperature High Pressure Water 期刊论文
ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 11, 页码: 1474-1484
作者:  Li Xiaohui;  Wang Jianqiu;  Han En-Hou;  Guo Yanjun;  Zheng Hui;  Yang Shuangliang
收藏  |  浏览/下载：159/0  |  提交时间：2021/02/02
alloy 690  high temperature high pressure water  corrosion  in situ scratch