Molten fuel-coolant interactions resulting from power transients in aluminium plate/water moderated reactors.

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dc.contributor.authorStorr, GJen_AU
dc.date.accessioned2007-11-22T04:25:47Zen_AU
dc.date.accessioned2010-04-30T04:37:01Zen_AU
dc.date.available2007-11-22T04:25:47Zen_AU
dc.date.available2010-04-30T04:37:01Zen_AU
dc.date.issued1989en_AU
dc.description.abstractThe behaviour of two reactors SL1 and SPERT D12 which underwent fast nuclear power transients prior to core destruction by a molten fuel-coolant interaction (MFCI) has been analysed and the results compared with measured data. The calculated spatial melt distribution and the mechanical work done during the events leads to high (approx 250 kJ/kg) conversion efficiencies for this type of interaction when compared with molten drop experiments. A simple model for the steam explosion using static thermodynamic properties of high temperature and pressure steam is used to calculate the dynamics of the reactors following the MFCI.en_AU
dc.identifier.citationStorr, G. J. (1989). Molten fuel-coolant interactions resulting from power transients in aluminium plate/water moderated reactors. Lucas Heights, NSW: Australian Nuclear Science and Technology Organisation.en_AU
dc.identifier.govdoc589en_AU
dc.identifier.isbn0642598967en_AU
dc.identifier.issn10307745en_AU
dc.identifier.otherANSTO-E-685en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/579en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Nuclear Science and Technology Organisationen_AU
dc.subjectReactorsen_AU
dc.subjectFuel elementsen_AU
dc.subjectMaterialsen_AU
dc.subjectTransientsen_AU
dc.subjectTransient overpower accidentsen_AU
dc.subjectMolten metal-water reactionsen_AU
dc.subjectReactor coresen_AU
dc.titleMolten fuel-coolant interactions resulting from power transients in aluminium plate/water moderated reactors.en_AU
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