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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  
Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel 期刊论文
ACTA METALLURGICA SINICA, 2017, 卷号: 53, 期号: 12, 页码: 1588-1602
作者:  Deng Ping;  Peng Qunjia;  Han En-Hou;  Ke Wei;  Sun Chen;  Xia Haihong;  Jiao Zhijie
收藏  |  浏览/下载:118/0  |  提交时间:2021/02/02
nuclear grade stainless steel  proton irradiation  dislocation loop  radiation-induced segregation  radiation-induced hardening  
Study of Irradiation Damage in Domestically Fabricated Nuclear Grade Stainless Steel 期刊论文
ACTA METALLURGICA SINICA, 2017, 卷号: 53, 期号: 12, 页码: 1588-1602
作者:  Deng Ping;  Peng Qunjia;  Han En-Hou;  Ke Wei;  Sun Chen;  Xia Haihong;  Jiao Zhijie
收藏  |  浏览/下载:117/0  |  提交时间:2021/02/02
nuclear grade stainless steel  proton irradiation  dislocation loop  radiation-induced segregation  radiation-induced hardening  
EFFECT OF Ni2+ IN OCCLUDED VOLUME ON THE OXIDATION BEHAVIOR OF 304 STAINLESS STEEL IN HIGH TEMPERATURE WATER 期刊论文
ACTA METALLURGICA SINICA, 2011, 卷号: 47, 期号: 7, 页码: 927-931
作者:  Kuang Wenjun;  Wu Xinqiang;  Han En-Hou
收藏  |  浏览/下载:77/0  |  提交时间:2021/02/02
nuclear-grade stainless steel  high temperature high pressure water  occluded volume  Ni2+  oxide film  
CORROSION BEHAVIORS OF NUCLEAR-GRADE STAINLESS STEEL AND FERRITIC-MARTENSITIC STEEL IN SUPERCRITICAL WATER 期刊论文
ACTA METALLURGICA SINICA, 2011, 卷号: 47, 期号: 7, 页码: 932-938
作者:  Zhong Xiangyu;  Wu Xinqiang;  Han En-Hou
收藏  |  浏览/下载:90/0  |  提交时间:2021/02/02
nuclear-grade stainless steel  ferritic-martensitic steel  supercritical water  corrosion  oxide film  
CORROSION FATIGUE OF NUCLEAR-GRADE STAINLESS STEEL IN HIGH TEMPERATURE WATER AND ITS ENVIRONMENTAL FATIGUE DESIGN MODEL 期刊论文
ACTA METALLURGICA SINICA, 2011, 卷号: 47, 期号: 7, 页码: 790-796
作者:  Wu Xinqiang;  Xu Song;  Han En-Hou;  Ke Wei
收藏  |  浏览/下载:68/0  |  提交时间:2021/02/02
nuclear-grade stainless steel  high temperature pressurized water  corrosion fatigue  environmentally assisted cracking  design model