Flow analysis and flow-induced vibration evaluation for low-pressure feedwater heater of a nuclear power plant

摘要: This paper performs a three-dimensional flow analysis and flow-induced vibration evaluation of tube bundle for the low-pressure feedwater heater nuclear power plant. Using commercial computational fluid dynamics software, CFX-4, detailed shell side model is first developed near-field cross around different locations within can be thus obtained. Additionally, cross-flow velocity then used to evaluate bundle. Mechanisms vortex shedding fluid-elastic instability are both taken into account by use an industry standard TEMA in this work. Flow margin avoid shown heater. The results will helpful performance, operation maintenance