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Evolution of fretting wear behavior of zirconium alloy cladding tube under gross slip regime in simulated primary water of pressurized water reactor 期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2025, 卷号: 220, 页码: 276-289
作者:  Zhang, Yusheng;  Ming, Hongliang;  Wang, Shuji;  Wu, Bin;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：4/0  |  提交时间：2025/04/27
Gross slip regime  Zirconium alloy tube  Microstructural evolution  Dynamic recrystallization  Grid-to-rod fretting  
Evolution of fretting wear behavior of zirconium alloy cladding tube under gross slip regime in simulated primary water of pressurized water reactor 期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2025, 卷号: 220, 页码: 276-289
作者:  Zhang, Yusheng;  Ming, Hongliang;  Wang, Shuji;  Wu, Bin;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：6/0  |  提交时间：2025/04/27
Gross slip regime  Zirconium alloy tube  Microstructural evolution  Dynamic recrystallization  Grid-to-rod fretting  
Study of fretting wear behavior of 690TT heat exchanger tube under three fretting regimes in high temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 605, 页码: 11
作者:  Zhang, Yusheng;  Wang, Shuji;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：1/0  |  提交时间：2025/04/27
Fretting regime  Running condition fretting map  Material response fretting map  690tt heat exchanger tube  High temperature pressurized water  
Effect of cold work level on the crack propagation behaviour of 316LN stainless steel in high-temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 17
作者:  Sun, Wei;  Wu, Bin;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：1/0  |  提交时间：2025/04/27
316LN stainless steel  Cold work  Stress corrosion cracking  High-temperature pressurized water  Crack propagation  
Effect of cold work level on the crack propagation behaviour of 316LN stainless steel in high-temperature pressurized water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2025, 卷号: 603, 页码: 17
作者:  Sun, Wei;  Wu, Bin;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：2/0  |  提交时间：2025/04/27
316LN stainless steel  Cold work  Stress corrosion cracking  High-temperature pressurized water  Crack propagation  
The radial delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tube at different temperatures 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2024, 卷号: 601, 页码: 11
作者:  Pan, Chunting;  Ming, Hongliang;  Shi, Xiuqiang;  Zhao, Guannan;  Bao, Yichen;  Meng, Fanjiang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：1/0  |  提交时间：2025/04/27
Zr-2.5Nb alloy  Pressure tube  Radial delayed hydrides cracking  
The radial delayed hydride cracking behavior of Zr-2.5Nb alloy pressure tube at different temperatures 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2024, 卷号: 601, 页码: 11
作者:  Pan, Chunting;  Ming, Hongliang;  Shi, Xiuqiang;  Zhao, Guannan;  Bao, Yichen;  Meng, Fanjiang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：1/0  |  提交时间：2025/04/27
Zr-2.5Nb alloy  Pressure tube  Radial delayed hydrides cracking  
Fretting wear behavior of Zr alloy cladding tube mated with Zr alloy dimple under mixed fretting regime in simulated primary water of PWR 期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2023, 卷号: 158, 页码: 43-52
作者:  Zhang, Yusheng;  Ming, Hongliang;  Lai, Jiang;  Gao, Lixia;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：7/0  |  提交时间：2024/01/07
Fretting wear  Mixed fretting regime  Zr alloy tube  High temperature pressurized water  Microstructure  
Insights into stress corrosion cracking in scratched area of alloy 690TT steam generator tubes 期刊论文
ACTA MATERIALIA, 2023, 卷号: 255, 页码: 16
作者:  Wu, Bin;  Zhang, Yusheng;  Meng, Fanjiang;  Zhang, Zhiming;  Li, Yifeng;  Wang, Jianqiu;  Han, En-Hou;  Ming, Hongliang
收藏  |  浏览/下载：11/0  |  提交时间：2024/01/07
Nickel based superalloys  Surface scratches  TEM  Stress corrosion cracking  Plastic deformation  
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