XS data preparation for 3D full core calculations

Abstract

Nuclear safety is the essential aspect of the nuclear power plant operation. The safety is based on the well prepared fuel loading pattern that is created with using 3D full core calculations. The calculations are conducted with the simplified geometry and simplified neutron transport solvers (called macrocodes) in industry based process. The simplified calculation approach is efficient with reduced calculation costs, however the specific library of the macroscopic cross-sections have to be prepared. The library is calculated using deterministic or stochastic lattice codes. The macroscopic cross-sections are affected by the calculation approach, moreover they provide connections of the mathematical solution with the physic meaning. The macroscopic cross-sections are compared in the paper. The main problem of the deterministic calculation codes is self-shielding simulation. The presented approach shows relatively good results consistency with the stochastic code. Otherwise, the XS are affected by the self-shielding methodology in higher scale than the multiplication factor. The XS calculated via different code represents reasonably good compliance, however the transport XS is highly affected by the approach (up to 30 %) or code used for data preparation process (up to 50%).