AUS burnup module char and the associated status data pool
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Date
1975-12
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
Australian Atomic Energy Commission
Abstract
The 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.
Description
Keywords
A codes, Burnup, Cross sections, Neutron flux, Neutrons
Citation
Robinson, G. S. (1975). AUS burnup module char and the associated status data pool (AAEC/E372). Lucas Heights, NSW: Australian Atomic Energy Commission.