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Failure Analysis of a Primary Reactor Cooling Pump Using Modal and Vibration Analysis

机译:基于模态和振动分析的主反应堆冷却泵故障分析

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Four pumps redundantly supply primary cooling water to the reactor of the High Flux Isotope Reactor (HFIR) at the Oak Ridge National Laboratory (ORNL). All four pumps underwent maintenance during a recently scheduled downtime. During preliminary evaluation following maintenance, one pump, PU-1A, exhibited higher vibration levels compared to the other three pumps. The pump, being a safety class item, underwent further performance testing to rule out potential damage resulting from the higher vibration. Vibration analysis and modal analysis including steady state spectrum, operational deflection shape, run up transients, and modal impact have been utilized to identify dynamic characteristics that could contribute to the increased vibration levels. This report will cover the testing setup, methodology, analysis results, and recommendations.
机译:四个泵向橡树岭国家实验室(ORNL)的高通量同位素反应堆(HFIR)的反应堆多余地供应一次​​冷却水。在最近计划的停机时间内,所有四个泵都进行了维护。在维护后的初步评估中,一个PU-1A泵比其他三个泵表现出更高的振动水平。作为安全等级的泵,泵进行了进一步的性能测试,以排除由于更高的振动而可能造成的损坏。振动分析和模态分析(包括稳态频谱,操作偏转形状,加速瞬变和模态冲击)已被用于识别可能有助于增加振动水平的动态特性。该报告将涵盖测试设置,方法,分析结果和建议。

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