Analysis of heat transfer to axial dispersed flow between rod bundles under reactor emergency cooling conditions

Journal Article · Fri Aug 01 04:00:00 EDT 1980 · J. Heat Transfer; (United States)

DOI:https://doi.org/10.1115/1.3244332· OSTI ID:6798586

Wong, S; Hochreiter, L E

Analysis is carried out for dispersed flow heat transfer under reactor emergency cooling conditions. The present formulation explicitly reveals an extra dependence of the heat transfer coefficient and Nusselt number on the mean vapor temperature for droplet dispersed flow which is not found in single phase flow heat transfer. The heat transfer results obtained from three different geometries: an infinite square array of cylindrical rods, an annulus and a circular pipe: are compared; all have the same hydraulic diameter. It is found that, within the framework of the present analysis, results for annulus and the rod bundles agree well when the pitch-to-diameter ratio is 1.5 or greater. The circular pipe is in general a poor approximation for rod bundle geometries except at a pitch-to-diameter ratio of about 1.3 which is typical of present day light water reactor fuel assemblies.

• Research Organization: Nuclear Technology Division, Westinghouse Corporation, Pittsburgh, Pennslvania 15230
• OSTI ID: 6798586
• Journal Information: J. Heat Transfer; (United States), Journal Name: J. Heat Transfer; (United States) Vol. 102:3; ISSN JHTRA
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220200 -- Nuclear Reactor Technology-- Components & Accessories
42 ENGINEERING
420400* -- Engineering-- Heat Transfer & Fluid Flow
ANALYTICAL SOLUTION
BOUNDARY CONDITIONS
CONVECTION
COOLING SYSTEMS
DISPERSIONS
DROPLETS
ENERGY TRANSFER
EQUATIONS
FLUID FLOW
FUEL ASSEMBLIES
FUEL ELEMENT CLUSTERS
HEAT TRANSFER
LAMINAR FLOW
MULTIPHASE FLOW
PARTICLES
RADIANT HEAT TRANSFER
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
ROD BUNDLES