AN ANALYTICAL REPRESENTATION FOR THE SOLUTION OF NEUTRON KINETIC TRANSPORT EQUATION IN SLAB-GEOMETRY MULTIGROUP DISCRETE ORDINATES FORMULATION

摘要

Presented here is a decomposition method based on series representation of the group angular fluxes and delayed neutron precursors in smoothly continuous functions for energy multigroups, slab-geometry discrete ordinates kinetics equations supplemented with a prescribed number of delayed neutron precursors. Numerical results to a non-reflected sub-critical slab stabilized by steady-state sources are given to illustrate the accuracy and efficiency of the offered method.