Research of Flow-Induced Vibration of Secondary Core Support Assembly of Reactors

The paper described the structures and functions of the secondary core support assembly (SCSA) of the reactor, and the events about the flow-induced vibration of SCSA happened in recent years. The FIV test of reactor internals model shows that the response of SCSA is the greatest response among the components of the whole reactor, and it is worthy of attention. SCSA of Qinshan Phase II is the same as that in the mainstream second generation nuclear power units in China, and the test and analysis results show that they are safe in FIV. Finally, the feasibility of elimination SCSA and the idea of design optimization are discussed, and the reliability and safety of the lower plenum structure are improved from the point of view of FIV, which provides reference for the improvement of SCSA structure design of the subsequent three-generation nuclear power units. (authors)