SOLUTION TECHNIQUE FOR NEUTRON AND GAMMA-QUANTUM TRANSPORT EQUATION AT TABULATED INPUT SCATTERING GROUP CROSS-SECTIONS AND ITS APPLICATION FOR THE VVER-1000 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. 51-63.
An algorithm able to find solutions of the multi-group radiation transport equation in multi-dimensional geometries with tabulated input scattering cross-sections is presented in the paper. The algorithm verification results obtained on a trivial model problem with smooth model scattering cross-sections are discussed. The paper presents neutron and gamma flux densities calculated using the scattering cross-sections, which satisfy the real laws of radiation/matter interaction in a small model problem with a point isotropic mono-energy source and protection of the VVER-1000 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 cross-sections.
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