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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：5/0  |  提交时间：2024/01/07
Fretting wear  Mixed fretting regime  Zr alloy tube  High temperature pressurized water  Microstructure  
Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR 期刊论文
ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2022, 页码: 16
作者:  Zhang, Yusheng;  Lai, Jiang;  Ming, Hongliang;  Gao, Lixia;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：61/0  |  提交时间：2023/05/09
Zirconium alloy tube  Fretting wear  Grid-to-rod  High-temperature pressurized water  Normal force  
Stress corrosion behavior of scratched Alloy 690TT steam generator tube in chlorine-containing high-temperature pressurized water 期刊论文
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2022, 页码: 12
作者:  Wu, Bin;  Meng, Fanjiang;  Zhang, Zhiming;  Li, Rongbo;  Ming, Hongliang;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：105/0  |  提交时间：2022/07/01
Alloy 690TT  chloride ions  high-temperature pressurized water  scratch  stress corrosion cracking  
Effect of the frequency on fretting corrosion behavior between Alloy 690TT tube and 405 stainless steel plate in high temperature pressurized water 期刊论文
TRIBOLOGY INTERNATIONAL, 2021, 卷号: 164, 页码: 16
作者:  Zhang, Yusheng;  Ming, Hongliang;  Tang, Lichen;  Wang, Jianqiu;  Qian, Hao;  Han, En-Hou
收藏  |  浏览/下载：134/0  |  提交时间：2021/11/22
Fretting corrosion  Fretting frequency  Alloy 690TT  High temperature pressurized water  
Corrosion Fatigue Behavior of 316LN Stainless Steel Hollow Specimen in High-Temperature Pressurized Water 期刊论文
ACTA METALLURGICA SINICA, 2021, 卷号: 57, 期号: 3, 页码: 309-316
作者:  Tan Jibo;  Wang Xiang;  Wu Xinqiang;  Han En-Hou
收藏  |  浏览/下载：127/0  |  提交时间：2021/10/15
corrosion fatigue  high-temperature pressurized water  stainless steel  hollow specimen  
Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water 期刊论文
MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2018, 卷号: 69, 期号: 3, 页码: 328-336
作者:  Zhu, RL;  Wang, JQ;  Ming, HL;  Zhang, ZM;  Han, EH;  Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, 62 Wencui Rd, Shenyang 110016, Liaoning, Peoples R China.
收藏  |  浏览/下载：104/0  |  提交时间：2018/06/05
High-temperature Water  Environmentally Assisted Cracking  Reactor Primary Water  Pwr Primary Water  Pressurized-water  Dissolved-oxygen  Oxidation Behavior  Nickel-alloys  Growth  Metal  
Structural, mechanical and corrosion studies of Cr-rich inclusions in 152 cladding of dissimilar metal weld joint 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 498, 页码: 9-19
作者:  Li, YF;  Wang, JQ;  Han, EH;  Yang, CD;  Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China.
收藏  |  浏览/下载：118/0  |  提交时间：2018/06/05
Pressurized-water Reactors  Environmentally-assisted Cracking  Safe-end  Quantitative Assessment  Secondary-side  Residual-stresses  High-temperature  Fusion Boundary  Base Alloys  Part 1  
Influence of later-dissolved oxygen on microstructural changes in oxide films formed on Alloy 690TT in hydrogenated primary water 期刊论文
Corrosion Science, 2015, 卷号: 94, 页码: 245-254
作者:  Z. M.;  Wang Zhang, J. Q.;  Han, E. H.;  Ke, W.
收藏  |  浏览/下载：97/0  |  提交时间：2015/05/08
Nickel  Sem  Tem  High Temperature Corrosion  Oxidation  High-temperature Water  Stress-corrosion Cracking  Ni-base Alloys  Reactor Primary Conditions  Type-316 Stainless-steel  Different  Surface-states  Simulated Primary Water  X-ray Photoelectron  Nickel-based Alloys  Pressurized-water  
Comparison of Corrosion Resistance of UNS N06690TT and UNS N08800SN in Simulated Primary Water with Various Concentrations of Dissolved Oxygen 期刊论文
Corrosion, 2014, 卷号: 70, 期号: 6, 页码: 598-614
作者:  J. Q. Wang;  X. H. Li;  F. Huang;  Z. M. Zhang;  J. Z. Wang;  R. W. Staehle
收藏  |  浏览/下载：147/0  |  提交时间：2014/07/03
Dissolved Oxygen  Electrochemical Impedance Spectroscopy  Pressurized  Water Reactor Primary Water  Uns N06690  Uns N08800  High-temperature  Alloy 690  Dissolution  Behavior  Cracking  Reactor  Films  
Influence of dissolved oxygen concentration on the oxide film formed on Alloy 690 in high temperature water 期刊论文
Corrosion Science, 2013, 卷号: 69, 页码: 197-204
作者:  W. J. Kuang;  X. Q. Wu;  E. H. Han
收藏  |  浏览/下载：139/0  |  提交时间：2013/12/24
Alloy  Sem  Xps  Oxidation  High Temperature Corrosion  Hydrogenated Water  Corrosion Behavior  Pressurized-water  Electrochemical Properties  Passive Films  Base Alloys  304-stainless-steel  Oxidation  Nickel  Reactors