Compilation of experimental burnout data for axial flow of water in rod bundles.

Abstract

A compilation has been made of burnout (critical heat flux) data from the results of more thant 12000 tests on 321 electrically-heated water-cooled experimental assemblies each simulating to some extent the operating or postulated accident conditions in the fuel elements of water-cooled nuclear power reactors. The main geometric characteristics of the assemblies are listed and references are given for the sources of information from which the data were gathered

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