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Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water 期刊论文
JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2022, 卷号: 120, 页码: 36-52
作者:  Lin, Xiaodong;  Peng, Qunjia;  Han, En-Hou;  Ke, Wei
收藏  |  浏览/下载：138/0  |  提交时间：2022/07/01
Stainless steel weld metal  Proton irradiation  Deformation microstructures  Irradiation assisted stress corrosion cracking  Grain and phase boundaries  
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel 期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 3, 页码: 349-361
作者:  Deng Ping;  Sun Chen;  Peng Qunjia;  Han En-Hou;  Ke Wei;  Rao Zhijie
收藏  |  浏览/下载：110/0  |  提交时间：2021/02/02
nuclear grade stainless steel  proton irradiation  localized deformation  corrosion  irradiation assisted stress corrosion cracking  
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel 期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 3, 页码: 349-361
作者:  Deng Ping;  Sun Chen;  Peng Qunjia;  Han En-Hou;  Ke Wei;  Rao Zhijie
收藏  |  浏览/下载：111/0  |  提交时间：2021/02/02
nuclear grade stainless steel  proton irradiation  localized deformation  corrosion  irradiation assisted stress corrosion cracking  
Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel 期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 3, 页码: 349-361
作者:  Deng Ping;  Sun Chen;  Peng Qunjia;  Han En-Hou;  Ke Wei;  Rao Zhijie
收藏  |  浏览/下载：137/0  |  提交时间：2021/02/02
nuclear grade stainless steel  proton irradiation  localized deformation  corrosion  irradiation assisted stress corrosion cracking  
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：106/0  |  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  
Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment 期刊论文
CORROSION SCIENCE, 2018, 卷号: 132, 页码: 9-20
作者:  Dong, LJ;  Peng, QJ;  Xue, H;  Han, EH;  Ke, W;  Wang, L;  Peng, QJ (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：199/0  |  提交时间：2018/06/05
Low-alloy Steel  High-temperature Water  Heat-affected Zone  Bwr Coolant Environments  Grain-boundary  Metal Weld  Assisted Cracking  Stainless-steel  Chromium Depletion  Residual-stress  
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：120/0  |  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  
Strain-rate dependent fatigue behavior of 316LN stainless steel in high-temperature water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 489, 页码: 33-41
作者:  Tan, Jibo;  Wu, Xinqiang;  Han, En-Hou;  Ke, Wei;  Wang, Xiang;  Sun, Haitao;  Wu, XQ (reprint author), Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Liaoning Key Lab Safety & Assessment Tech Nucl Ma, Shenyang 110016, Peoples R China.
收藏  |  浏览/下载：115/0  |  提交时间：2017/08/17
316ln Stainless Steel  Corrosion Fatigue  Strain Rate  High-temperature Water  Environmentally Assisted Cracking  
Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment 期刊论文
Journal of Nuclear Materials, 2014, 卷号: 446, 期号: 1-3, 页码: 15-26
作者:  L. T. Zhang;  J. Q. Wang
收藏  |  浏览/下载：116/0  |  提交时间：2014/04/18
High-temperature Water  Assisted Cracking  Alloy 690tt  Pure Water  Growth  Behavior  Dependence  Chemistry  Coolant  Model  
Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water 期刊论文
Corrosion Science, 2014, 卷号: 89, 页码: 203-213
作者:  J. B. Tan;  X. Q. Wu;  E. H. Han;  W. Ke;  X. Q. Liu;  F. J. Meng;  X. L. Xu
收藏  |  浏览/下载：151/0  |  提交时间：2015/01/14
Alloy  Sem  Corrosion Fatigue  High Temperature Corrosion  Environmentally Assisted Cracking  Low-cycle Fatigue  Austenitic  Stainless-steels  Pressure-vessel Steels  Reactor Conditions  Dissolved-oxygen  Growth Behavior  Initiation  Mechanisms  Prediction