机构

• 力学研究所 [4]
• 上海应用物理研究所 [3]
• 金属研究所 [2]
• 近代物理研究所 [2]

采集方式

• OAI收割 [11]

内容类型

• 期刊论文 [11]

发表日期

• 2021 [2]
• 2019 [3]
• 2018 [2]
• 2017 [1]
• 2014 [1]
• 2012 [1]
• 更多

学科主题

筛选

浏览/检索结果: 共11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 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：70/0  |  提交时间：2021/11/01 Reactor pressure vessel steel  Primary coolant environment  Low cycle fatigue  Corrosion fatigue  Environmental fatigue correction factor   An Object Kinetic Monte Carlo Simulation for Defect Evolution of Neutron-Irradiated Reactor Pressure Vessel Steels: Carbon Sensitive Study 期刊论文  OAI收割 PHYSICA STATUS SOLIDI B-BASIC SOLID STATE PHYSICS, 2021, 页码: 6 作者:  Li, Jianyang;  Zhang, Chonghong;  Yang, Yitao;  Wang, Tieshan;  Ignacio, Martin-Bragado   |  收藏  |  浏览/下载：62/0  |  提交时间：2021/12/08 irradiation defects  reactor pressure vessel model alloys  simulations  solute concentrations   Specimen size effect on the ductile-brittle transition reference temperature of A508-3 steel 期刊论文  OAI收割 THEORETICAL AND APPLIED FRACTURE MECHANICS, 2019, 卷号: 104, 页码: 8 作者:  Zhou ZY;  Tong ZF;  Qian GA(钱桂安);  Berto F   |  收藏  |  浏览/下载：65/0  |  提交时间：2020/03/11 Reactor pressure vessel steel  Fracture toughness  Ductile-brittle transition reference temperature  Size effect  J-Q theory   Modelling of reactor pressure vessel subjected to pressurized thermal shock using 3D-XFEM 期刊论文  OAI收割 NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 353, 页码: 13 作者:  Niceno B;  Jaros M;  Qian GA(钱桂安);  Niffenegger M;  Mora DF   |  收藏  |  浏览/下载：82/0  |  提交时间：2019/11/26 Pressurized thermal shock  Large Break LOCA  Stress intensity factor  Reactor pressure vessel  Fracture mechanics  XFEM   Irradiation effect on impact fracture behavior of A508-3 steel in ductile-to-brittle transition range 期刊论文  OAI收割 ENGINEERING FAILURE ANALYSIS, 2019, 卷号: 97, 页码: 836-843 作者:  Zhou ZY;  Tong ZF   |  收藏  |  浏览/下载：86/0  |  提交时间：2019/04/11 Reactor pressure vessel  Neutron embrittlement  Crack propagation  Plastic deformation  Charpy impact test  Scanning electron microscopy   Stress and thickness calculation of a bolted flat cover with double metal sealing rings 期刊论文  OAI收割 NUCLEAR SCIENCE AND TECHNIQUES, 2018, 卷号: 29, 期号: 8, 页码: - 作者:  Wang, XY;  Zhu, SF;  Wang, X;  Zhang, XC   |  收藏  |  浏览/下载：25/0  |  提交时间：2019/12/17 REACTOR PRESSURE-VESSEL  PERFORMANCE   Temperature dependence of nickel ion irradiation damage in GH3535 alloy weld metal 期刊论文  OAI收割 JOURNAL OF NUCLEAR MATERIALS, 2017, 卷号: 497, 期号: -, 页码: 108-116 作者:  Huang, HF;  Zhou, XL;  Li, CW;  Gao, J;  Wei, T   |  收藏  |  浏览/下载：181/0  |  提交时间：2018/08/30 Radiation-induced Segregation  Austenitic Stainless-steels  Pressure-vessel Steels  Microstructural Evolution  Elevated-temperature  Beam Irradiation  Elastic-modulus  Indentation  Hardness  Reactor   Corrosion fatigue behavior of Alloy 690 steam generator tube in borated and lithiated high temperature water 期刊论文  OAI收割 Corrosion Science, 2014, 卷号: 89, 页码: 203-213 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：33/0  |  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   Positron annihilation study of proton-irradiated reactor pressure vessel steels 期刊论文  OAI收割 RADIATION PHYSICS AND CHEMISTRY, 2012, 卷号: 81, 期号: 10, 页码: 1586-1592 作者:  Liu, XB;  Wang, XT;  Zhang, CH   |  收藏  |  浏览/下载：26/0  |  提交时间：2015/10/15 Positron annihilation  Reactor pressure vessel steel  Proton irradiation  Defect