CHAR and BURNMAC - burnup modules of the AUS neutronics code system

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dc.contributor.authorRobinson, GSen_AU
dc.date.accessioned2007-11-22T04:06:22Zen_AU
dc.date.accessioned2010-04-30T04:42:55Zen_AU
dc.date.available2007-11-22T04:06:22Zen_AU
dc.date.available2010-04-30T04:42:55Zen_AU
dc.date.issued1986-03en_AU
dc.description.abstractIn the AUS neutronics code system the burnup module CHAR solves the nuclide depletion equations by an analytic technique in a number of spatial zones. CHAR is usually used as one component of a lattice burnup calculation but contains features which also make it suitable for some global burnup calculations. BURNMAC is a simple accounting module based on the assumption that cross sections for a rector zone depend only on irradiation. BURNMAC is used as one component of a global calculation in which burnup is achieved by interpolation in the cross sections produced from a previous lattice calculation.en_AU
dc.identifier.citationBurnupen_AU
dc.identifier.citationRobinson, G. S. (1986). CHAR and BURNMAC - burnup modules of the AUS neutronics code system (AAEC/E624). Lucas Heights, NSW: Australian Atomic Energy Commission.en_AU
dc.identifier.govdoc955en_AU
dc.identifier.isbn0642598266en_AU
dc.identifier.otherAAEC-E-624en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/24en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectAnalytical solutionen_AU
dc.subjectB codesen_AU
dc.subjectC codesen_AU
dc.subjectNeutron fluxen_AU
dc.subjectNuclear fuelsen_AU
dc.subjectIsotopesen_AU
dc.titleCHAR and BURNMAC - burnup modules of the AUS neutronics code systemen_AU
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