The invention provides a flow-induced vibration and fretting wear coupling analysis calculating method for a U-shaped heat transfer tube of nuclear power station steam generators. The method is characterized by comprising heat transfer tube-antivibration strip fretting wear test, flow-induced vibration analysis and fretting wear calculation analysis. By means of the flow-induced vibration and fretting wear coupling analysis calculating method for a U-shaped heat transfer tube of nuclear power station steam generators of the invention, the calculation and analysis of flow-induced vibration and fretting wear of heat transfer tubes are coupled, determining and considering whether fluid elasticity instability will happen if tube walls become thin and antivibration strip support turns weak. At the same time, the wearing condition of heat transfer tubes for a long time can be predicted under the changing flow-induced vibration condition.