Neutron transport with anisotropic scattering

Research output: ThesisDoctoral thesis

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Abstract

The Boltzmann neutron transport equation with arbitrary order anisotropic scattering is solved using the Case/Mika singular eigenfunction expansion (SEE). In order to do so, one needs to compute all discrete eigenvalues. A numerically stable and efficient method is proposed to do this in a two-step process: first the number of discrete eigenvalues is calculated and this provides a stopping criterion in the second phase: the solution of the characteristic equation for the discrete eigenvalues. The method was improved to be able to locate so-called near-singular eigenvalues (eigenvalues lying extremely close to the continuum [-1,+1]. Next to the discrete part, one also needs the continuum part. This is characterised by its angular Legendre moments and a stable and efficient method has been proposed to calculate these moments. Three applications were studied: the boundary sources method, a study of the discrete spectrum of the Henyey-Greenstein kernel and two challenges in radiative transfer.

Details

Original languageEnglish
Awarding Institution
  • VUB - Vrije Universiteit Brussel
Supervisors/Advisors
Place of PublicationUniversité Libre de Bruxelles
Publisher
  • ULB - Université Libre de Bruxelles
Publication statusPublished - 12 May 2005

Keywords

  • neutron transport, anisotropic scattering, singuler eigenfunction expansion, boundary sources method

ID: 207770