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.
|Original language||English (US)|
|Title of host publication||Unknown Host Publication Title|
|Number of pages||12|
|State||Published - 1985|
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