Keywords: fast breeder reactors, FBR, similarity, thermal hydraulics, modelling laws, liquid sodium-cooled reactors, India, temperature patterns, flow-induced vibration, scale models, reactor assembly, simulation, nuclear technology, nuclear energy, nuclear power
Comprehensive scale model for LMFBR reactor assembly thermal hydraulics
The construction of the 500 MWe Prototype Fast Breeder Reactor (PFBR) is underway at Kalpakkam, India. This liquid sodium-cooled reactor is a pool-type reactor with two secondary loops. Experimental investigations have been carried out to understand the complex flow, temperature patterns and flow-induced vibration characteristics. To enhance the confidence in the design of the components immersed in the pool of the reactor and to reduce the scale effects, a large scale model was constructed. The Scale Model for Reactor Thermal Hydraulics (SAMRAT) is a one-by-four scaled-down model of the reactor assembly of PFBR. This model is a unique one in that it attempts to investigate multiple phenomena using a single model. This paper describes the details of the model – the scaling criteria adopted, the simulation for each study, and the methodology of the study and the salient features of the model – and examines the results.