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

Research output: Contribution to journalArticle

27 Citations (Scopus)

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
StatePublished - Feb 1986

Fingerprint

Neutrons
Polynomials
Scattering
Geometry

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

Cite this

@article{4d3dcd507a3e42028af38f069e49e47e,
title = "SOLUTION OF THE ONE-GROUP TIME-DEPENDENT NEUTRON TRANSPORT EQUATION IN AN INFINITE MEDIUM BY POLYNOMIAL RECONSTRUCTION.",
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.",
author = "Ganapol, {Barry D}",
year = "1986",
month = "2",
language = "English (US)",
volume = "92",
pages = "272--279",
journal = "Nuclear Science and Engineering",
issn = "0029-5639",
publisher = "American Nuclear Society",
number = "2",

}

TY - JOUR

T1 - SOLUTION OF THE ONE-GROUP TIME-DEPENDENT NEUTRON TRANSPORT EQUATION IN AN INFINITE MEDIUM BY POLYNOMIAL RECONSTRUCTION.

AU - Ganapol, Barry D

PY - 1986/2

Y1 - 1986/2

N2 - 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.

AB - 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.

UR - http://www.scopus.com/inward/record.url?scp=0022659669&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0022659669&partnerID=8YFLogxK

M3 - Article

AN - SCOPUS:0022659669

VL - 92

SP - 272

EP - 279

JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

SN - 0029-5639

IS - 2

ER -