Open AccessExperimental analysis of pressure drop and flow redistribution in axial flows in rod bundles
Author(s) -
Carlos Bastos Franco,
Pedro Carajilescov
Publication year - 2000
Publication title -
revista brasileira de ciências mecânicas
Language(s) - English
Resource type - Journals
ISSN - 0100-7386
DOI - 10.1590/s0100-73862000000400009
Subject(s) - rod , pressure drop , mechanics , axial symmetry , inlet , drag , materials science , flow (mathematics) , coolant , control rod , bundle , structural engineering , engineering , mechanical engineering , physics , composite material , medicine , alternative medicine , pathology
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