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Influence of chromium of low content on the corrosion behavior of SA106B carbon steels in high-temperature pressurized LiOH medium 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2023, 卷号: 414, 页码: 10
作者:  Zheng, Kexin;  Hu, Hongxiang;  Wang, Zhengbin;  Zheng, Yugui;  Shang, Xianhe;  Zhang, Wei;  Zhao, Liang
收藏  |  浏览/下载：2/0  |  提交时间：2025/04/27
Electrochemical measurements  Nuclear power plant  Carbon Steel  Lithium hydroxide corrosion  High-temperature corrosion  Oxidation  
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：7/0  |  提交时间：2024/01/08
bearing  cage  fatigue fracture  finite element calculation  nuclear power plant  
Oxidation Behavior of GH984G Alloy in Steam at 700 degrees C 期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 7, 页码: 893-901
作者:  Wang Changshuai;  Guo Lili;  Tang Liying;  Zhou Rongcan;  Guo Jianting;  Zhou Lanzhang
收藏  |  浏览/下载：128/0  |  提交时间：2021/02/02
GH984G alloy  Ni-Fe-Cr base alloy  steam oxidation  700 degrees C ultra-supercritical coal-fired power plant  
Oxidation Behavior of GH984G Alloy in Steam at 700 degrees C 期刊论文
ACTA METALLURGICA SINICA, 2019, 卷号: 55, 期号: 7, 页码: 893-901
作者:  Wang Changshuai;  Guo Lili;  Tang Liying;  Zhou Rongcan;  Guo Jianting;  Zhou Lanzhang
收藏  |  浏览/下载：135/0  |  提交时间：2021/02/02
GH984G alloy  Ni-Fe-Cr base alloy  steam oxidation  700 degrees C ultra-supercritical coal-fired 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：143/0  |  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：161/0  |  提交时间：2021/02/02
High-entropy alloys  Alloy design  Mechanical properties  Nuclear power plant  Accident tolerant fuel  
Multi-boiler System Optimization in Integrated Steelworks Based on Decomposition and Coordination Method 期刊论文
JOURNAL OF IRON AND STEEL RESEARCH INTERNATIONAL, 2015, 卷号: 22, 期号: 3, 页码: 226-231
作者:  Ma Guangyu;  Sun Wenqiang;  Li Weidong;  Ye Zhu;  Cai Jiuju
收藏  |  浏览/下载：93/0  |  提交时间：2021/02/26
GAS  MODEL  IRON  boiler  self-owned power plant  integrated steelworks  decomposition and coordination method  
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：122/0  |  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  
Experimental and computational failure analysis of a valve in a nuclear power plant 期刊论文
Engineering Failure Analysis, 2012, 卷号: 22, 页码: 41284
作者:  C. B. Liu;  S. L. Jiang;  Y. G. Zheng
收藏  |  浏览/下载：98/0  |  提交时间：2013/02/05
Carbon Steel  Cavitation Erosion  Flow-accelerated Corrosion  Power  Plant  Valve Failures  
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：88/0  |  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