Keywords: prototype fast breeder reactors, PFBR, flow-induced vibrations, FIV, vortex shedding, fluid elastic instability, steam generators, modal analysis, natural frequencies, probability density function, PDF, power spectral density, PSD, nuclear reactors, nuclear energy, nuclear power, heat exchangers
Experimental investigation of flow-induced vibration in PFBR steam generator sector model
The 500 MWe Prototype Fast Breeder Reactor (PFBR) is under construction at Kalpakkam. It is a liquid metal sodium-cooled pool-type fast reactor with all primary components located inside a sodium pool. Fission heat is transferred to a secondary sodium system in an intermediate heat exchanger, which is in turn transferred to water in a Steam Generator (SG). The PFBR-SG is a vertical shell and tube-type heat exchanger with sodium in its shell side and water in the tube side. Flow-Induced Vibration (FIV) experiments were carried out in a water test loop on a 60-degree sector model to validate the design and also to qualify the component for plant operation.