Development of multi-group spectral code TVS-M
21st Symposium of AER on VVER Reactor Physics and Reactor Safety (2011, Dresden, Germany)
Spectral and core calculations
Abstract
This paper is dedicated to the latest version of TVS-M code ? TVS-M 2007, which
allows the neutron flux distribution inside fuel assemblies to be calculated without using the
diffusion approximation. The new spatial calculation module PERST introduced in TBS-M
code is based on the first collisions probability (FCP) method and allows the scattering
anisotropy to be accounted for.
This paper presents some preliminary results calculated with the use of the new
version of TVS-M code.