AUS burnup module char and the associated status data pool

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dc.contributor.authorRobinson, GSen_AU
dc.date.accessioned2007-11-22T04:25:49Zen_AU
dc.date.accessioned2010-04-30T04:37:03Zen_AU
dc.date.available2007-11-22T04:25:49Zen_AU
dc.date.available2010-04-30T04:37:03Zen_AU
dc.date.issued1975-12en_AU
dc.description.abstractThe CHAR module of the AUS reactor neutronics scheme solves the multiregion nuclide depletion equations using an analytic method. The module obtains cross section, flux and geometry data from AUS data pools, and uses the STATUS data pool which has been designed for the storage of nuclide compositions, spatial smearing factors and other miscellaneous information.en_AU
dc.identifier.citationRobinson, G. S. (1975). AUS burnup module char and the associated status data pool (AAEC/E372). Lucas Heights, NSW: Australian Atomic Energy Commission.en_AU
dc.identifier.govdoc591en_AU
dc.identifier.isbn0642997241en_AU
dc.identifier.otherAAEC-E-372en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/581en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectA codesen_AU
dc.subjectBurnupen_AU
dc.subjectCross sectionsen_AU
dc.subjectNeutron fluxen_AU
dc.subjectNeutronsen_AU
dc.titleAUS burnup module char and the associated status data poolen_AU
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