Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 92 / Number 2 / Pages 272-279
B. D. Ganapol
Nuclear Science and Engineering / Volume 92 / Number 2 / Pages 272-279
Format:electronic copy (download)
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 beam sources, 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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