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

B. D. Ganapol

doi:10.13182/NSE86-A18176

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

B. D. Ganapol

Research output: Contribution to journal › Article › peer-review

30 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 language	English (US)
Pages (from-to)	272-279
Number of pages	8
Journal	Nuclear Science and Engineering
Volume	92
Issue number	2
DOIs	https://doi.org/10.13182/NSE86-A18176
State	Published - 1986

ASJC Scopus subject areas

Nuclear Energy and Engineering

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10.13182/NSE86-A18176

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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.",

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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.

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U2 - 10.13182/NSE86-A18176

DO - 10.13182/NSE86-A18176

M3 - Article

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SN - 0029-5639

VL - 92

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JO - Nuclear Science and Engineering

JF - Nuclear Science and Engineering

IS - 2

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

Abstract

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