机构

• 力学研究所 [5]
• 金属研究所 [4]
• 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 [12]

内容类型

• 期刊论文 [11]
• 会议论文 [1]

发表日期

• 2021 [2]
• 2019 [4]
• 2018 [2]
• 2012 [1]
• 2009 [1]
• 2006 [1]
• 更多

学科主题

筛选

浏览/检索结果: 共12条，第1-10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;  Li JH(李江华);  Cong, Tao;  Sun JY(孙经雨)   |  收藏  |  浏览/下载：57/0  |  提交时间：2021/11/01 Reactor pressure vessel steel  Primary coolant environment  Low cycle fatigue  Corrosion fatigue  Environmental fatigue correction factor   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   Effect of Annealing on Microstructure of Thermally Aged 308L Stainless Steel Weld Metal 期刊论文  OAI收割 ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 5, 页码: 555-565 作者:  Lin Xiaodong;  Peng Qunjia;  Han En-Hou;  Ke Wei   |  收藏  |  浏览/下载：51/0  |  提交时间：2021/02/02 stainless steel weld metal  thermal ageing  annealing  spinodal decomposition  G phase precipitation  phase boundary segregation   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   Analysis on stress and deformation of large-scale concentric recuperator for high-temperature PbLi loop 期刊论文  OAI收割 INTERNATIONAL JOURNAL OF ENERGY RESEARCH, 2018, 卷号: 42, 期号: 7, 页码: 2583-2592 作者:  Huang, Shaoqiu;  Zhu, Zhiqiang;  Huang, Wangli   |  收藏  |  浏览/下载：49/0  |  提交时间：2019/08/23 concentric recuperator  deformation  DRAGON-V  stress intensity   A new local approach to cleavage fracture and its application in a reactor pressure vessel 会议论文  OAI收割 Belgrade, SERBIA, AUG 26-31, 2018 作者:  Qian GA(钱桂安);  Lei WS;  Zhu SP;  Correia J;  De Jesus A   |  收藏  |  浏览/下载：26/0  |  提交时间：2019/04/19 Ferritic steels  cleavage fracture  notch brittleness  statistical model   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;  Jiang, J;  Wu, YC   |  收藏  |  浏览/下载：19/0  |  提交时间：2015/10/15 Positron annihilation  Reactor pressure vessel steel  Proton irradiation  Defect   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