机构

• 金属研究所 [35]

采集方式

• OAI收割 [35]

内容类型

• 期刊论文 [35]

发表日期

• 2022 [2]
• 2021 [4]
• 2020 [8]
• 2019 [9]
• 2017 [6]
• 2016 [1]
• 更多

学科主题

• Metallurgy... [5]
• Materials ... [4]
• Materials ... [1]

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浏览/检索结果: 共35条，第1-10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 Deformation and cracking behaviors of proton-irradiated 308L stainless steel weld metal strained in simulated PWR primary water 期刊论文  OAI收割 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：95/0  |  提交时间：2022/07/01 Stainless steel weld metal  Proton irradiation  Deformation microstructures  Irradiation assisted stress corrosion cracking  Grain and phase boundaries   Effect of thermal ageing and dissolved gas on corrosion of 308L stainless steel weld metal in simulated PWR primary water 期刊论文  OAI收割 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2022, 卷号: 96, 页码: 308-324 作者:  Lin, Xiaodong;  Peng, Qunjia;  Han, Yaolei;  Han, En-Hou;  Ke, Wei   |  收藏  |  浏览/下载：44/0  |  提交时间：2022/07/01 Stainless steel weld metal  Thermal ageing  Corrosion  High temperature water  TEM   Environmentally assisted cracking in the fusion boundary region of a SA508-Alloy 52M dissimilar weld joint in simulated primary pressurized water reactor environments 期刊论文  OAI收割 CORROSION SCIENCE, 2021, 卷号: 190, 页码: 13 作者:  Dong, Lijin;  Zhang, Yan;  Han, Yaolei;  Peng, Qunjia;  Han, En-Hou   |  收藏  |  浏览/下载：39/0  |  提交时间：2021/10/15 A  Nickel  A  Low alloy steel  B  TEM  C  Stress corrosion  C  Corrosion fatigue  C  Welding   Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021) 期刊论文  OAI收割 SCIENTIFIC REPORTS, 2021, 卷号: 11, 期号: 1, 页码: 1 作者:  Deng, Ping;  Peng, Qunjia;  Han, En-Hou   |  收藏  |  浏览/下载：15/0  |  提交时间：2021/10/15 Proton irradiation assisted localized corrosion and stress corrosion cracking in 304 nuclear grade stainless steel in simulated primary PWR water 期刊论文  OAI收割 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2021, 卷号: 65, 页码: 61-71 作者:  Deng, Ping;  Peng, Qunjia;  Han, En-Hou;  Ke, Wei;  Sun, Chen   |  收藏  |  浏览/下载：17/0  |  提交时间：2021/03/15 Stainless steel  AFM  TEM  High temperature corrosion  Stress corrosion   Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor 期刊论文  OAI收割 SCIENTIFIC REPORTS, 2021, 卷号: 11, 期号: 1, 页码: 9 作者:  Deng, Ping;  Peng, Qunjia;  Han, En-Hou   |  收藏  |  浏览/下载：17/0  |  提交时间：2021/10/15 Effect of post-irradiation annealing on microstructure and corrosion of proton-irradiated 308L stainless steel weld metal 期刊论文  OAI收割 CORROSION SCIENCE, 2020, 卷号: 175, 页码: 17 作者:  Lin, Xiaodong;  Han, En-Hou;  Peng, Qunjia;  Ke, Wei;  Jiao, Zhijie   |  收藏  |  浏览/下载：25/0  |  提交时间：2021/02/02 Stainless steel  TEM  High temperature corrosion  Segregation  Welding   Effect of post-irradiation annealing on microstructure and corrosion of proton-irradiated 308L stainless steel weld metal 期刊论文  OAI收割 CORROSION SCIENCE, 2020, 卷号: 175, 页码: 17 作者:  Lin, Xiaodong;  Han, En-Hou;  Peng, Qunjia;  Ke, Wei;  Jiao, Zhijie   |  收藏  |  浏览/下载：25/0  |  提交时间：2021/02/02 Stainless steel  TEM  High temperature corrosion  Segregation  Welding   Effect of post-irradiation annealing on microstructure and corrosion of proton-irradiated 308L stainless steel weld metal 期刊论文  OAI收割 CORROSION SCIENCE, 2020, 卷号: 175 作者:  Lin, Xiaodong;  Han, En-Hou;  Peng, Qunjia;  Ke, Wei;  Jiao, Zhijie   |  收藏  |  浏览/下载：19/0  |  提交时间：2021/01/11 Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water 期刊论文  OAI收割 ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2020, 页码: 13 作者:  Deng, Ping;  Han, En-Hou;  Peng, Qunjia;  Sun, Chen   |  收藏  |  浏览/下载：22/0  |  提交时间：2021/02/02 Stainless steel  Irradiation  High-temperature corrosion  Intergranular corrosion