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Flow Induced Vibration Theory & Analysis and Fuel Rod Cumulative Damage Function

流致震动理论分析与燃烧棒累积损伤函数计算
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摘要 Brief description of research in nuclear engineering,the safety of reactor design is very important.The structure inside the reactor and coolant constitute a complex fluid solid coupling system,so the flow induced vibration(FIV)is inevitable.In this paper,the specific influence of FIV,such as vibration amplitude,frequency,structural stablity,nonlinear dynamic characteristics,etc,and analysis and computational method for the influence of structural vibration damage are studied and discussed.In the end,two methods of measuring the FIV and some strategies for vibration suppression design in the future development are summed up.The cladding of fuel rod is regard as the first safety barrier in nuclear reactor,and it is important to do its life analysis and calculation.
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出处 《IMP & HIRFL Annual Report》 2017年第1期198-199,共2页 中国科学院近代物理研究所和兰州重离子研究装置年报(英文版)
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