Studies on flow induced vibration of reactivity devices of 700 MWe Indian PHWR

Component failures due to excessive flow-induced vibration are still affecting the performance and reliability of nuclear power stations. Tube failures due to fretting-wear in nuclear steam generators, and vibration related damage of reactor internals are of particular concern. In the Indian nuclear industry, flow induced vibrations are assessed early in the design process and the results are incorporated in the design procedures. In this paper the details of flow induced vibration studies on internals like liquid zone control unit and poison injection units of heavy water filled calandria of 700 MWe Indian pressurized heavy water reactor is given. This includes computational fluid dynamics studies from which the velocities are extracted for the components lying inside the calandria. With these velocities as input, further studies are performed to predict the dynamic behavior of these components. Results of these calculations as well as conclusions derived from this investigation are presented. Based on the studies it has been established that flow induced vibration is not a concern in the present design of 700 MWe calandria internals.

► FIV studies on internals of heavy water filled calandria of 700 MWe Indian PHWR is presented.
► This includes CFD and structural dynamic analysis to predict the dynamic behavior of component lying inside calandria.
► Results of these calculations as well as conclusions from this investigation are presented.
► It is established that FIV is not a concern in the present design of calandria internals.