机构

• 金属研究所 [8]

采集方式

• OAI收割 [8]

内容类型

• 期刊论文 [8]

发表日期

• 2019 [3]
• 2017 [2]
• 2011 [3]

学科主题

筛选

浏览/检索结果: 共8条，第1-8条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择题名升序题名降序提交时间升序提交时间降序作者升序作者降序发表日期升序发表日期降序 Study on Irradiation Assisted Stress Corrosion Cracking of Nuclear Grade 304 Stainless Steel 期刊论文  OAI收割 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   |  收藏  |  浏览/下载：16/0  |  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  OAI收割 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   |  收藏  |  浏览/下载：17/0  |  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  OAI收割 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   |  收藏  |  浏览/下载：22/0  |  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  OAI收割 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   |  收藏  |  浏览/下载：39/0  |  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  OAI收割 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   |  收藏  |  浏览/下载：35/0  |  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  OAI收割 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：16/0  |  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  OAI收割 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：10/0  |  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  OAI收割 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：18/0  |  提交时间：2021/02/02 nuclear-grade stainless steel  high temperature pressurized water  corrosion fatigue  environmentally assisted cracking  design model