Abstract: Detailed thermal hydraulic investigations are very
essential for safe and reliable functioning of liquid metal cooled fast
breeder reactors. These investigations are further more important for
components with complex profile, since there is no direct correlation
available in literature to evaluate the hydraulic characteristics of such
components directly. In those cases available correlations for similar
profile or geometries may lead to significant uncertainty in the
outcome. Hence experimental approach can be adopted to evaluate
these hydraulic characteristics more precisely for better prediction in
reactor core components.
Prototype Fast Breeder Reactor (PFBR), a sodium cooled pool
type reactor is under advanced stage of construction at Kalpakkam,
India. Several components of this reactor core require hydraulic
investigation before its usage in the reactor. These hydraulic
investigations on full scale models, carried out by experimental
approaches using water as simulant fluid are discussed in the paper.