Multigroup Neutron Transport using a Collision-Based Hybrid Method

TL;DR

This paper introduces a collision-based hybrid algorithm for multigroup neutron transport that combines coarse and fine grid discretizations to improve computational efficiency in time-dependent problems.

Contribution

It extends a collision-based hybrid method to multigroup neutron transport, coupling coarse and fine grid equations for enhanced efficiency.

Findings

More efficient than traditional multigroup methods in various scenarios

Effective for time-dependent problems with diverse materials and geometries

Demonstrated improvements across multiple energy groups

Abstract

A collision-based hybrid algorithm for the discrete ordinates approximation of the neutron transport equation is extended to the multigroup setting. The algorithm uses discrete energy and angle grids at two different resolutions and approximates the fission and scattering sources on the coarser grids. The coupling of a collided transport equation, discretized on the coarse grid, with an uncollided transport equation, discretized on the fine grid, yields an algorithm that, in most cases, is more efficient than the traditional multigroup approach. The improvement over existing techniques is demonstrated for time-dependent problems with different materials, geometries, and energy groups.