AUS98 - the 1998 version of the AUS modular neutronics code system

Abstract

AUS is a neutronics code system which may be used for calculations of a wide range of fission reactors, fusion blankets and other neutron applications. The present version, AUS98, has a nuclear cross section library based on ENDF/B-VI and includes modules which provide for reactor lattice calculations, one-dimensional transport calculations, multidimensional diffusion calculations, cell and whole reactor burnup calculations, and flexible editing of results, calculations of multi-region resonance shielding, coupled neutron and photon transport, energy deposition, fission product inventory and neutron diffusion are combined within the one code system. This report gives details of all system aspects of AUS and all modules except the POW3D multidimensional diffusion module.