Analysis of Flow-Induced Vibration of Nuclear Reactor Internals
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摘要: 以某新型工程试验堆为研究对象,采用试验分析与仿真计算相结合的手段探索该试验堆堆内构件流致振动特性。在流致振动试验中,根据相似准则建立了1/2的缩比试验模型,并在整体水力模拟台架上开展了100%额定流量工况下的堆内构件流致振动试验,测量了吊篮组件和二次支承组件在流体作用下的动力响应;根据吊篮组件和二次支承组件所受激励的不同,结合试验结果分别采用不同的计算方法得到了流体力作用下结构的动力响应,分别获得了100%额定流量工况下的最大应力值。Abstract: The flow-induced vibration characteristic of a new nuclear reactor was analyzed in this paper by performing dynamic test and numerical calculation. A 1/2 scaled-down model of a new designed nuclear reactor was manufactured for performing the dynamic test with the hydrodynamics simulation system at the 100% operation condition. And the dynamical responses of core barrel and secondary core support structure were measured in the test. Based on the results of the dynamic test, a three-dimensional finite element model of the reactor internals for the numerical analysis was constructed to obtain the max strains and stresses of core barrel and secondary core support structure at the 100% operation condition.
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