SOLUTION OF THE ONE-GROUP TIME-DEPENDENT NEUTRON TRANSPORT EQUATION IN AN INFINITE MEDIUM BY POLYNOMIAL RECONSTRUCTION.

Research output: Contribution to journalArticlepeer-review

27 Scopus citations

Abstract

The numerical solution to the one-group time-dependent neutron transport equation in infinite plane, spherical, and cylindrical geometries is obtained via an expansion in Legendre polynomials. The computation features general anisotropic scattering, isotropic and beamsources, and a power law time-dependent cross-section variation. Results for test problems are compared with previously obtained numerical solutions and with the diffusion approximation.

Original languageEnglish (US)
Pages (from-to)272-279
Number of pages8
JournalNuclear Science and Engineering
Volume92
Issue number2
DOIs
StatePublished - Jan 1 1986

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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