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首页> 外文期刊>International Journal of Pressure Vessels and Piping >Flow analysis and flow-induced vibration evaluation for low-pressure feedwater heater of a nuclear power plant
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Flow analysis and flow-induced vibration evaluation for low-pressure feedwater heater of a nuclear power plant

机译：核电站低压给水加热器的流量分析和流致振动评估

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摘要

This paper performs a three-dimensional flow analysis and flow-induced vibration evaluation of a tube bundle for the low-pressure feedwater heater of a nuclear power plant. Using a commercial computational fluid dynamics software, CFX-4, a detailed shell side flow analysis model is first developed and the near-field cross flow around different locations of the tube bundle within a feedwater heater can be thus obtained. Additionally, the cross-flow velocity is then used to evaluate the flow-induced vibration of the tube bundle. Mechanisms of vortex shedding and fluid-elastic instability are both taken into account by use of an industry standard TEMA in this work. Flow velocity margin to avoid the flow-induced vibration can be thus shown in different locations of the low-pressure feedwater heater. The analysis results will be helpful for the evaluation of performance, operation and maintenance of the low-pressure feedwater heater of a nuclear power plant.
机译：本文对核电厂低压给水加热器的管束进行三维流动分析和流动诱发振动评估。使用商业计算流体动力学软件CFX-4，首先开发了详细的壳侧流分析模型，从而可以得到给水加热器内管束不同位置周围的近场横流。另外，横流速度然后用于评估管束的流动引起的振动。在这项工作中，使用行业标准的TEMA均考虑了涡旋脱落和流体弹性不稳定性的机制。因此，可以在低压给水加热器的不同位置显示避免流动引起的振动的流速裕度。分析结果将有助于评估核电站低压给水加热器的性能，运行和维护。

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