An analysis of self-terminating power transients in the reactor HIFAR

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dc.contributor.authorConnolly, JWen_AU
dc.contributor.authorFerguson, HDen_AU
dc.date.accessioned2007-11-22T04:12:48Zen_AU
dc.date.accessioned2010-04-30T04:27:49Zen_AU
dc.date.available2007-11-22T04:12:48Zen_AU
dc.date.available2010-04-30T04:27:49Zen_AU
dc.date.issued1978-02en_AU
dc.description.abstractConsequences of step reactivity additions above critical have been calculated for HIFAR under conditions of no coolant flow and the operating coolant flow rate of 400 kgs. In particular, the maximum core excess reactivity that will allow loss of a central coarse control arm blade from the core has been determined. In order to perform these calculations a cylindrical geometry version of the neutron kinetics, heat transfer code ZAPP has been written and tested against the experimental data from the SPERT III-E oxide core. The results of this comparison are given as an appendix to this report.en_AU
dc.identifierAAEC-E-435en_AU
dc.identifier.citationConnolly, J. W., Ferguson, H. (1978). An analysis of self-terminating power transients in the reactor HIFAR (AAEC/E435). Lucas Heights, NSW: Australian Atomic Energy Commission, Research Establishment.en_AU
dc.identifier.govdoc73en_AU
dc.identifier.isbn0642596441en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/109en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectHIFAR Reactoren_AU
dc.subjectCriticalityen_AU
dc.subjectReactivity insertionsen_AU
dc.subjectTransientsen_AU
dc.subjectReactor coresen_AU
dc.titleAn analysis of self-terminating power transients in the reactor HIFARen_AU
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