Experimental analysis of pressure drop and flow redistribution in axial flows in rod bundles
AUTOR(ES)
Franco, Carlos Bastos, Carajilescov, Pedro
FONTE
Journal of the Brazilian Society of Mechanical Sciences
DATA DE PUBLICAÇÃO
2000
RESUMO
Fuel elements of PWR type nuclear reactors consist of rod bundles, arranged in a square array, and held by spacer grids. The coolant flows, mainly, axially along the rods. Although such elements are laterally open, experiments are performed in closed type test sections, originating the appearance of subchannels with different geometries. In the present work, utilizing a test section of two bundles of 4x4 pins each, experiments were performed to determine the friction and the grid drag coefficients for the different subchannels and to observe the effect of the grids in the crossflow, in cases of inlet flow maldistribution.
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