Please use this identifier to cite or link to this item: https://apo.ansto.gov.au/dspace/handle/10238/223
Title: A guide to the AUS modular neutronics code system.
Authors: Robinson, GS
Keywords: Computer codes
Fission
Computer calculations
Three-dimensional calculations
Burnup
Issue Date: Apr-1987
Publisher: Australian Atomic Energy Commission
Citation: Robinson, G. S. (1987). A guide to the AUS modular neutronics code system (AAEC/E645). Lucas Heights, NSW: 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.
Gov't Doc #: 352
URI: http://apo.ansto.gov.au/dspace/handle/10238/223
ISBN: 0642598630
Appears in Collections:Scientific and Technical Reports

Files in This Item:
File Description SizeFormat 
AAEC-E-645.pdf1.47 MBAdobe PDFThumbnail
View/Open


Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.