Study on flow induced vibration response of reactor core barrel

The problem of flow induced vibration in reactor structures has long been closely concerned by the nuclear engineering community, and its adverse effects can lead to fatigue damage to the structure, which may have effects on reactor safe operation. In order to study the flow induced vibration response of the Hualong-1 reactor core barrel (CB), the fluid excitation force acting on the CB is first analyzed based on CFD method and then a finite element model of the basket is established using ANSYS. Finally, its dynamic response under fluid excitation was studied, and the influence of the CB under the fluid action of the reactor internals was comprehensively evaluated. Stress analysis shows that the maximum flow induced stress intensity at each position of the CB is less than the fatigue stress limit, indicating that the structure is safe. Comparing the calculated results with the experimental results, the results are in good agreement.