Abstract
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.
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