Compilation of Experimental Burnout Data for Axial Flow of Water in Rod Bundles.

摘要

A compilation has been made of burnout (critical heat flux) data from the results of more than 12,000 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. (Atomindex citation 12:622663)