A guide to the AUS modular neutronics code system.
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Date
1987-04
Authors
Journal Title
Journal ISSN
Volume Title
Publisher
Australian Atomic Energy Commission
Abstract
A general description is given of the AUS modular neutronics code system which may be used for calculations of a very wide range of fission reactors fusion blankets and other neutron applications. The present system has cross-section libraries derived from ENDF/B-IV and includes modules which provide for lattice calculations one-dimensional transport calculations and one two and three-dimensional diffusion calculations burnup calculations and the flexible editing of results. Details of all system aspects of AUS are provided but the major individual modules are only outlined. Sufficient information is given to enable other modules to be added to the system.
Description
Keywords
Computer codes, Fission, Computer calculations, Three-dimensional calculations, Burnup
Citation
Robinson, G. S. (1987). A guide to the AUS modular neutronics code system (AAEC/E645). Lucas Heights, NSW: Australian Atomic Energy Commission.