机构

• 力学研究所 [3]
• 金属研究所 [2]
• 上海应用物理研究所 [2]

采集方式

• OAI收割 [7]

内容类型

• 期刊论文 [6]
• 会议论文 [1]

发表日期

• 2021 [1]
• 2020 [2]
• 2018 [1]
• 2017 [1]
• 2016 [1]
• 2014 [1]
• 更多

学科主题

• Materials ... [1]
• Metallurgy... [1]

筛选

浏览/检索结果: 共7条，第1-7条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择提交时间升序提交时间降序发表日期升序发表日期降序题名升序题名降序作者升序作者降序 Effect of environmental media on the fatigue property of Chinese A508-3 steel of AP1000 期刊论文  OAI收割 INTERNATIONAL JOURNAL OF FRACTURE, 2021, 页码: 10 作者:  Ning, Guangsheng;  Zhong, Weihua;  Li JH(李江华);  Cong, Tao;  Sun JY(孙经雨)   |  收藏  |  浏览/下载：58/0  |  提交时间：2021/11/01 Reactor pressure vessel steel  Primary coolant environment  Low cycle fatigue  Corrosion fatigue  Environmental fatigue correction factor   Fatigue model of domestic 316LN steel in simulated primary coolant environment of CAP1400 期刊论文  OAI收割 INTERNATIONAL JOURNAL OF FATIGUE, 2020, 卷号: 130, 页码: 6 作者:  Zhong WH;  Qian GA(钱桂安);  Tong ZF;  Wu WW;  Zhu SP   |  收藏  |  浏览/下载：36/0  |  提交时间：2020/03/21 Primary coolant pipe  Low cycle fatigue  Corrosion fatigue  Fatigue model  Environmental fatigue life   Fatigue model of domestic 316LN steel in simulated primary coolant environment of CAP1400 会议论文  OAI收割 Univ Porto, Fac Engn, Porto, PORTUGAL, SEP 05-07, 2018 作者:  Zhong,Weihua;  Qian GA(钱桂安);  Tong,Zhenfeng;  Wu,Wenwang;  Zhu,ShunPeng   |  收藏  |  浏览/下载：14/0  |  提交时间：2022/11/24 Primary coolant pipe  Low cycle fatigue  Corrosion fatigue  Fatigue model  Environmental fatigue life   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  OAI收割 CORROSION SCIENCE, 2018, 卷号: 132, 页码: 9-20 作者:  Dong, LJ;  Peng, QJ;  Xue, H;  Han, EH;  Ke, W   |  收藏  |  浏览/下载：65/0  |  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   Radionuclides in primary coolant of a fluoride salt-cooled high-temperature reactor during normal operation 期刊论文  OAI收割 NUCLEAR SCIENCE AND TECHNIQUES, 2017, 卷号: 28, 期号: 3, 页码: - 作者:  Zhang, GQ;  Wang, S;  Zhang, HQ;  Zhu, XW;  Peng, C   |  收藏  |  浏览/下载：19/0  |  提交时间：2018/08/30 3D microstructures of nuclear graphite: IG-110, NBG-18 and NG-CT-10 期刊论文  OAI收割 NUCLEAR SCIENCE AND TECHNIQUES, 2016, 卷号: 27, 期号: 3, 页码: - 作者:  Jing, SP;  Zhang, C;  Pu, J;  Jiang, HY 收藏  |  浏览/下载：18/0  |  提交时间：2017/03/02 X-ray tomography  3D pore network structure  Permeability   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  OAI收割 Journal of Nuclear Materials, 2014, 卷号: 446, 期号: 1-3, 页码: 15-26 L. T. Zhang; J. Q. Wang 收藏  |  浏览/下载：21/0  |  提交时间：2014/04/18 high-temperature water  assisted cracking  alloy 690tt  pure water  growth  behavior  dependence  chemistry  coolant  model