Application of Cross Section Distribution Function to the Estimation of Flux at a Point for Radiation Transport Problem

Results of Monte Carlo test calculations on the influence of energy structure cross sections on the estimation of flux at a point is demonstrated. The problem of deep penetration of neutrons through iron slabs with different thicknesses is solved. Calculations were performed with a special MORSE multigroup Monte Carlo code, which uses group constants of ABBN library and the distribution functions of the cross sections in the subgroup approach. The calculation results show that subgroup approach application to neutron data permits an increase in the accuracy of the estimation of flux at a point.