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Numerical prediction of flow induced vibrations in nuclear reactor applications

机译:核反应堆应用中流致振动的数值预测

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Flow induced vibration (FIV) plays an important role in nuclear industry. In nuclear reactors, the FIV are caused by a strong interaction between the fuel rods and the turbulent coolant flow around these rods. Numerical prediction of these strongly coupled fluid structure interaction (FSI) has been a challenge and is the main focus of this work. In this article, three aspects of FSI problems are numerically studied. In this first part, two different coupling schemes namely IQN-ILS and Guess-Seidel are thoroughly assessed for a laminar flow single rod experiment performed by Vattenfall (Lillberg et al. 2015). As a next step, a turbulent flow single rod experiment is selected to assess the capabilities of two different RANS models, i.e. a linear k - omega SST and a non-linear Reynolds Stress Model. Lastly, an application based experiment of Chen and Wambsganns (1972) is selected to validate the combined effect of the selected RANS model along with the coupling method. (C) 2017 Elsevier B.V. All rights reserved.
机译:流致振动(FIV)在核工业中起着重要作用。在核反应堆中,FIV是由燃料棒和围绕这些棒的湍急冷却剂流之间的强相互作用引起的。这些强耦合流体结构相互作用(FSI)的数值预测一直是一个挑战,并且是这项工作的主要重点。本文对FSI问题的三个方面进行了数值研究。在第一部分中,对Vattenfall进行的层流单杆实验彻底评估了两种不同的耦合方案,即IQN-ILS和Guess-Seidel(Lillberg等人,2015)。下一步,选择湍流单杆实验来评估两个不同的RANS模型(即线性k-omega SST和非线性雷诺应力模型)的能力。最后,选择了Chen和Wambsganns(1972)的基于应用的实验,以验证所选RANS模型与耦合方法的组合效果。 (C)2017 Elsevier B.V.保留所有权利。

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