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

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dc.contributor.authorChapman, AGen_AU
dc.contributor.authorCarrard, Gen_AU
dc.date.accessioned2007-11-22T04:18:55Zen_AU
dc.date.accessioned2010-04-30T04:33:24Zen_AU
dc.date.available2007-11-22T04:18:55Zen_AU
dc.date.available2010-04-30T04:33:24Zen_AU
dc.date.issued1981-02en_AU
dc.description.abstractA 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.en_AU
dc.identifier.citationChapman, 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.en_AU
dc.identifier.govdoc390en_AU
dc.identifier.isbn0642597065en_AU
dc.identifier.otherAAEC-E-500en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/307en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectBurnouten_AU
dc.subjectWateren_AU
dc.subjectFuel element clustersen_AU
dc.subjectCritical heat fluxen_AU
dc.subjectFuel elementsen_AU
dc.subjectReactorsen_AU
dc.titleA compilation of experimental burnout data for axial flow of water in rod bundlesen_AU
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