研究论文
Probabilistic prediction of fretting-wear damage of nuclear fuel rods
P. Rubiolo
Westinghouse Electric (United States)
来源Nuclear Engineering and Design
年份2006
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学科主题
工程Mechanical stress and fatigue analysis
Vibration and Dynamic Analysis · Dynamics and Control of Mechanical Systems
参考文献 18
Fuel assembly self-excited vibration and test methodology
被引 3Ru-dong Lu, K. D. Broach, Jaakko McEvoy · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information) · 2004
Flow Induced Vibration and Fretting Wear in PWR Fuel
被引 16S. J. King, Michael Y. Young, D. D. Seel · 10th International Conference on Nuclear Engineering, Volume 1 · 2002
Fundamentals of Vibrations
被引 1,204L. Meirovitch, RG Parker · Applied Mechanics Reviews · 2001
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引用本文 47
A review of fretting study on nuclear power equipment
被引 220Zhen-bing Cai, Zhengyang Li, Meigui Yin · Tribology International · 2019
Autoclave grid-to-rod fretting corrosion behaviors of the Zr alloy fuel cladding with and without Cr coating through advanced characterization
被引 82Yahuan Zhao, Yaxiong Bai, Jie Yang · Corrosion Science · 2024
Fretting wear behavior of a nuclear fuel rod under a simulated primary coolant condition
被引 60Young-Ho Lee, Hyung-Kyu Kim · Wear · 2013
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