An Accurate S$_N$ Method for Solving Static Multigroup Neutron Transport Equations in Slab Geometry

TL;DR

This paper introduces a precise S_N solver for slab geometry neutron transport problems that accurately computes angular fluxes in constant cross-section regions without fine meshes or solution approximations.

Contribution

It provides a novel S_N method that improves accuracy in slab geometry neutron transport calculations without requiring mesh refinement.

Findings

Accurate angular fluxes in constant cross-section regions

No need for fine meshes or approximation of solution forms

Enhanced computational efficiency

Abstract

This paper presents an accurate S$_N$ solver for slab geometry. For constant cross-section regions, it gives accurate angular fluxes without need of fine meshes or approximation of solution forms.