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Effect of Normal Force on Fretting Wear Behavior of Zirconium Alloy Tube in Simulated Primary Water of PWR 期刊论文
Authors:  Zhang, Yusheng;  Lai, Jiang;  Ming, Hongliang;  Gao, Lixia;  Wang, Jianqiu;  Han, En-Hou
Favorite  |  View/Download:7/0  |  Submit date:2023/05/09
Zirconium alloy tube  Fretting wear  Grid-to-rod  High-temperature pressurized water  Normal force  
Effects of surface grinding for scratched alloy 690TT tube in PWR nuclear power plant: Microstructure and stress corrosion cracking 期刊论文
Authors:  Wu, Bin;  Ming, Hongliang;  Meng, Fanjiang;  Li, Yifeng;  He, Guangqing;  Wang, Jianqiu;  Han, En-Hou
Favorite  |  View/Download:53/0  |  Submit date:2022/07/01
Alloy 690TT  Scratch  Surface  Stress corrosion  High temperature corrosion  Intergranular corrosion  
Reaction Mechanism of High-Temperature Corium Pool of Core 期刊论文
RARE METAL MATERIALS AND ENGINEERING, 2022, 卷号: 51, 期号: 3, 页码: 913-920
Authors:  Xue Baoquan;  Yang Yaqian;  Liang Tian;  Chen Bo;  Ma Yingche;  Liu Kui;  Shan Hongyi;  Kang Taifeng;  Gu Peiwen
Favorite  |  View/Download:62/0  |  Submit date:2022/07/01
nuclear power safety  severe accident  in-vessel corium retention  molten zirconia  stratification mechanism  
Effect of Dilution Ratio of the First 309L Cladding Layer on the Microstructure and Mechanical Properties of Weld Joint of Connecting Pipe-Nozzle to Safe-End in Nuclear Power Plant 期刊论文
ACTA METALLURGICA SINICA, 2020, 卷号: 56, 期号: 8, 页码: 1057-1066
Authors:  Zhang Maolong;  Lu Yanhong;  Chen Shenghu;  Rong Lijian;  Lu Hao
Favorite  |  View/Download:94/0  |  Submit date:2021/02/02
buttering welding  dilution ratio  microstructure  mechanical property  cracking mechanism  
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
Authors:  Ming, Hongliang;  Zhang, Zhiming;  Wang, Jianqiu;  Han, En-Hou
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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
Authors:  Xiang, C.;  Han, E-H;  Zhang, Z. M.;  Fu, H. M.;  Wang, J. Q.;  Zhang, H. F.;  Hu, G. D.
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High-entropy alloys  Alloy design  Mechanical properties  Nuclear power plant  Accident tolerant fuel  
某核电厂楔形闸板阀阀瓣表面司太立合金堆焊层失效分析 期刊论文
腐蚀科学与防护技术, 2019, 卷号: 31.0, 期号: 006, 页码: 622-630
Authors:  张敏;  明洪亮;  王凡;  张志明;  王俭秋;  韩恩厚;  吕群贤
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失效分析  司太立合金  堆焊层  阀瓣  
Precise Determination of Trace Hydrogen in SA508-3 Steel for Nuclear Reactor Pressure Vessels 期刊论文
SCIENCE OF ADVANCED MATERIALS, 2018, 卷号: 10, 期号: 11, 页码: 1651-1657
Authors:  Hao, Luhan;  Zhao, Wei;  Peng, Yan;  Sun, Mingyue;  Li, Dianzhong;  Liu, Hu;  Wang, Xiaojing;  Umar, Ahmad;  Guo, Zhanhu
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Determination  Trace Hydrogen  SA508-3 Steel  Nuclear Reactor Pressure Vessels  
Evaluation of Fatigue Properties of CA6NM Martensite Stainless Steel Using Miniature Specimens 期刊论文
ACTA METALLURGICA SINICA, 2018, 卷号: 54, 期号: 10, 页码: 1359-1367
Authors:  Ma Yefei;  Song Zhuman;  Zhang Siqian;  Chen Lijia;  Zhang Guangping
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martensite stainless steel  fatigue property  miniature specimen  size effect  nuclear power material  
Research Progress on Sulfur-Induced Corrosion of Alloys 690 and 800 in High Temperature and High Pressure Water 期刊论文
ACTA METALLURGICA SINICA, 2017, 卷号: 53, 期号: 12, 页码: 1541-1554
Authors:  Xia Dahai;  Song Shizhe;  Wang Jianqiu;  Luo Jingli
Favorite  |  View/Download:65/0  |  Submit date:2021/02/02
steam generator  alloy 690  alloy 800  thiosulfate  reduced sulfur  passive film