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A compilation of experimental burnout data for axial flow of water in rod bundles

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Australian Atomic Energy Commission

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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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Chapman, A. G., & Carrard, G. (1981). A compilation of experimental burnout data for axial flow of water in rod bundles (AAEC/E500). Lucas Heights, NSW: Australian Atomic Energy Commission, Research Establishment.

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