AP1000 Steam Generator Tubes Experiments And Analysis Of Flow Induced Vibration

Fluid-structure interaction is the interaction phenomenon of the nuclear reactor coolant flow and structural vibration. The fluid-structure interaction research involves fluid mechanics and structural mechanics. Fluid-structure interaction is one of the frontal topics in the mechanics research. Flow induced vibration which widely exists in nuclear power plant is refers to the vibration of nuclear power plant equipment and components under the action of fluid-structure coupling. Fluid-structure interaction exists widely in nuclear plant. The flow internal fluid in PWR steam generator will cause the vibration of the U-tubes. Serious vibration can cause consequences such as heat exchange tube fracture which would affect safety and reliable operation of the reactor. So the research of U-shaped tubes flow-induced vibration phenomena is necessary.In the experiment, test section contains three single-tubes. The size of single-tube model is based on the actual size of PWR steam generator U-tubes. The test conditions can be changed by changing the water flow and intake air. We measure the vibration of tubes at different locations by using eddy current sensor. We can obtain vibration regular pattern of the tubes at different locations through the analysis of experimental data.