Thermal shock testing of ceramic balls representing pebble bed reactor fuel elements

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dc.contributor.authorWhatham, JFen_AU
dc.date.accessioned2007-11-22T04:22:03Zen_AU
dc.date.accessioned2010-04-30T04:34:29Zen_AU
dc.date.available2007-11-22T04:22:03Zen_AU
dc.date.available2010-04-30T04:34:29Zen_AU
dc.date.issued1973-08en_AU
dc.description.abstractA number of sintered ceramic beryllium oxide balls were heated and then quenched in fast-flowing carbon dioxide gas to determine the thermal stress which would crack similar balls containing a small amount of uranium dioxide fuel in the core of a prospective pebble bed nuclear reactor. The stress to crack the average ball was determined using simplifying assumptions, and as the balls were quenched in groups this stress will be used to calculate the allowable heat output of fuel balls in a pebble bed reactor.en_AU
dc.identifier.citationWhatham, J. F. (1973). Thermal shock testing of ceramic balls representing pebble bed reactor fuel elements. (AAEC/E231). Lucas Heights, NSW: Australian Atomic Energy Commission, Researchen_AU
dc.identifier.govdoc458en_AU
dc.identifier.isbn0642995877en_AU
dc.identifier.otherAAEC-E-231en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/420en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectBeryllium oxidesen_AU
dc.subjectThermal testingen_AU
dc.subjectCarbon dioxideen_AU
dc.subjectSimulationen_AU
dc.subjectThermal shocken_AU
dc.titleThermal shock testing of ceramic balls representing pebble bed reactor fuel elementsen_AU
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