Solution of the Monoenergetic Neutron Transport Equation in a Half Space
Barry Ganapol

TL;DR
This paper presents a new precise numerical method for solving the monoenergetic neutron transport equation in a half-space using Lagrange interpolation, offering an alternative to existing analytical and numerical approaches.
Contribution
It introduces a fundamental discretization approach based solely on Lagrange interpolation for the half-space neutron transport problem, improving accuracy and efficiency.
Findings
Achieves highly precise numerical solutions for the half-space neutron transport equation.
Provides an alternative to singular eigenfunction expansion and iterative methods.
Demonstrates effectiveness for the albedo problem with a vacuum boundary source.
Abstract
The analytical solution of neutron transport equation has fascinated mathematicians and physicists alike since the Milne half-space problem was introduce in 1921 [1]. Numerous numerical solutions exist, but understandably, there are only a few analytical solutions, with the prominent one being the singular eigenfunction expansion (SEE) introduced by Case [2] in 1960. For the half-space, the method, though yielding, an elegant analytical form resulting from half-range completeness, requires numerical evaluation of complicated integrals. In addition, one finds closed form analytical expressions only for the infinite medium and half-space cases. One can find the flux in a slab only iteratively. That is to say, in general one must expend a considerable numerical effort to get highly precise benchmarks from SEE. As a result, investigators have devised alternative methods, such as the CN [3],…
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Taxonomy
TopicsNuclear reactor physics and engineering · Nuclear Physics and Applications · Thermodynamic and Structural Properties of Metals and Alloys
