SOLUTION TECHNIQUE FOR NEUTRON AND GAMMAQUANTUM TRANSPORT EQUATION AT TABULATED INPUT SCATTERING GROUP CROSSSECTIONS AND ITS APPLICATION FOR THE VVER1000 REACTOR PROTECTION
O. V. Nikolayeva, L. P. Bass, V. S. Kuznetsov, V. V. Sinitsa, V. I. Tsofin VANT. Ser.: Mat. Mod. Fiz. Proc 2010. Вып.2. С. 5163.
An algorithm able to find solutions of the multigroup radiation transport equation in multidimensional geometries with tabulated input scattering crosssections is presented in the paper. The algorithm verification results obtained on a trivial model problem with smooth model scattering crosssections are discussed. The paper presents neutron and gamma flux densities calculated using the scattering crosssections, which satisfy the real laws of radiation/matter interaction in a small model problem with a point isotropic monoenergy source and protection of the VVER1000 reactor area. It is shown in the paper how the flux densities change when passing from the tabulated input data to their polynomial representation.Keywords: transport equation, angular dependence of scattering crosssections.
