机构

• 力学研究所 [4]
• 金属研究所 [2]
• 近代物理研究所 [2]
• 合肥物质科学研究院 [1]

采集方式

• OAI收割 [9]

内容类型

• 期刊论文 [9]

发表日期

• 2021 [2]
• 2020 [1]
• 2019 [3]
• 2017 [1]
• 2009 [1]
• 2006 [1]
• 更多

学科主题

筛选

浏览/检索结果: 共9条，第1-9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 Characterization of microstructures and mechanical property of Fe-ion-irradiated China A508-3 steel 期刊论文  OAI收割 NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS, 2021, 卷号: 504, 页码: 14-20 作者:  Ding, Z. N.;  Han, X. X.;  Yang, Y. T.;  Chen, Y. G.;  Zhang, X. L.   |  收藏  |  浏览/下载：48/0  |  提交时间：2021/12/08 RPV steel  Ion irradiation  Microstructure  Hardening   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   |  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   Internal friction study on precipitation/dissolution of Mn-Ni-Si phase in aged RPV model steel 期刊论文  OAI收割 MATERIALS LETTERS, 2020, 卷号: 269 作者:  Wu, Yinxing;  Hao, Ting;  Sun, Meng;  Jiang, Weibin;  Wang, Xianping   |  收藏  |  浏览/下载：32/0  |  提交时间：2020/11/26 Mn-Ni-Si precipitation  Thermal aging  Diffusion  Grain boundaries   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：52/0  |  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：68/0  |  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;  Qian GA(钱桂安);  Zhong WH;  Wang CL   |  收藏  |  浏览/下载：71/0  |  提交时间：2019/04/11 Reactor pressure vessel  Neutron embrittlement  Crack propagation  Plastic deformation  Charpy impact test  Scanning electron microscopy   Positron annihilation lifetime studies of stainless steel under proton and Xe irradiation 期刊论文  OAI收割 FUSION ENGINEERING AND DESIGN, 2017, 卷号: 120, 页码: 34-38 作者:  Xu, Chaoliang;  Zhang, Guodong;  Qian, Wangjie;  Mei, Jinna;  Liu, Xiangbing   |  收藏  |  浏览/下载：27/0  |  提交时间：2018/05/31 Stainless steel  Irradiation  Open volume defects  Lifetime   Effects of dynamic strain aging on mechanical properties of SA508 class 3 reactor pressure vessel steel 期刊论文  OAI收割 Journal of Materials Science, 2009, 卷号: 44, 期号: 11, 页码: 2882-2889 S. Xu; X. Q. Wu; E. H. Han; W. Ke 收藏  |  浏览/下载：11/0  |  提交时间：2012/04/13 high-temperature water  316l stainless-steel  deformation-behavior  tensile properties  activation-energy  jerky flow  alloy  fatigue  fracture  model   Influence of surface finish on fatigue cracking behavior of reactor pressure vessel steel in high temperature water 期刊论文  OAI收割 Materials and Corrosion-Werkstoffe Und Korrosion, 2006, 卷号: 57, 期号: 11, 页码: 868-871 X. Q. Wu; H. Guan; E. H. Han; W. Ke; Y. Katada 收藏  |  浏览/下载：12/0  |  提交时间：2012/04/14 environmentally assisted cracking  low-cycle fatigue  low-alloy  corrosion-fatigue  growth-behavior  carbon