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Fracture Analysis and Working Stress Calculation of Bearing Cage Used in Charging Pump in a Nuclear Power Plant 期刊论文
METALS, 2023, 卷号: 13, 期号: 8, 页码: 14
作者:  Chen, Qiang;  Jiang, Shengli;  Duan, Deli
收藏  |  浏览/下载：6/0  |  提交时间：2024/01/08
bearing  cage  fatigue fracture  finite element calculation  nuclear power plant  
Microstructure of a domestically fabricated dissimilar metal weld joint (SA508-52M-309L-CF8A) in nuclear power plant 期刊论文
MATERIALS CHARACTERIZATION, 2019, 卷号: 148, 页码: 100-115
作者:  Ming, Hongliang;  Zhang, Zhiming;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：141/0  |  提交时间：2021/02/02
Dissimilar metal weld joint  GTAW  Microstructure  Duplex stainless steel  Nuclear power plant  
Design of single-phase high-entropy alloys composed of low thermal neutron absorption cross-section elements for nuclear power plant application 期刊论文
INTERMETALLICS, 2019, 卷号: 104, 页码: 143-153
作者:  Xiang, C.;  Han, E-H;  Zhang, Z. M.;  Fu, H. M.;  Wang, J. Q.;  Zhang, H. F.;  Hu, G. D.
收藏  |  浏览/下载：159/0  |  提交时间：2021/02/02
High-entropy alloys  Alloy design  Mechanical properties  Nuclear power plant  Accident tolerant fuel  
Effect of carbon and niobium on the microstructure and impact toughness of a high silicon 12% Cr ferritic/martensitic heat resistant steel 期刊论文
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing, 2014, 卷号: 616, 页码: 12-19
作者:  Z. F. Ye;  P. Wang;  D. Z. Li;  Y. T. Zhang;  Y. Y. Li
收藏  |  浏览/下载：121/0  |  提交时间：2015/01/14
High Silicon 12% Cr Ferritic/martensitic Steel  Primary Nbc  Carbonitride  Thermodynamic Calculations  Impact Toughness  Ferritic Martensitic Steels  Si-enriched Steels  Mechanical-properties  Lead-bismuth  Power-plant  Corrosion-resistance  Nuclear-reactors  Creep  Strength  Temperature  Precipitation  
RESEARCH TRENDS ON MICRO AND NANO-SCALE MATERIALS DEGRADATION IN NUCLEAR POWER PLANT 期刊论文
ACTA METALLURGICA SINICA, 2011, 卷号: 47, 期号: 7, 页码: 769-776
作者:  Han En-Hou
收藏  |  浏览/下载：87/0  |  提交时间：2021/02/02
key material in nuclear power plant  stainless steel  nickel-based alloy  low alloy steel  zirconium alloy  corrosion  stress corrosion cracking  corrosion fatigue  flow assisted corrosion  irradiation degradation  
Predicting the preferential sites to liquid droplet erosion of the bellows assemblies by CFD 期刊论文
Nuclear Engineering and Design, 2011, 卷号: 241, 期号: 6, 页码: 2295-2306
作者:  H. X. Hu;  Y. G. Zheng;  C. B. Liu
Adobe PDF(3651Kb)  |  收藏  |  浏览/下载：113/0  |  提交时间：2012/04/13
Nuclear-power-plant  U-shaped Bellows  Wear Sites  Feedwater Heater  Failure Analysis  Disturbed Flow  Ductile Metals  Corrosion  Impact  Hydrodynamics  
CORROSION MECHANISMS OF STAINLESS STEEL AND NICKEL BASE ALLOYS IN HIGH TEMPERATURE HIGH PRESSURE WATER 期刊论文
ACTA METALLURGICA SINICA, 2010, 卷号: 46, 期号: 11, 页码: 1379-1390
作者:  Han En-Hou;  Wang Jianqiu;  Wu Xinqiang;  Ke Wei
收藏  |  浏览/下载：67/0  |  提交时间：2021/02/02
stainless steel  nickle base alloy  corrosion  stress corrosion  electrochemistry  nuclear power plant  surface oxide film