In the SG (steam generator) of PWR (pressurized water reactor) for a nuclear plant, hundreds of Ushaped tubes are used for the heat exchanger system. They interact with primary pressurized cooling water flow, generating flow-induced vibration in the secondary flow region. A simplified U-tube model is proposed in this study to apply for experiment and its counterpart computation. Using the commercial code, ANSYS-CFX, we first verified the Moody chart, comparing the straight pipe theory with the results derived from CFD (computational fluid dynamics) analysis. | Low-frequency modes in the fluid-structure interaction of a U-tube model for the steam generator in a PWR
