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 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 |
| Publisher | ANS |
| Pages | 696-707 |
| Number of pages | 12 |
| ISBN (Print) | 0894481177 |
| State | Published - 1985 |
ASJC Scopus subject areas
- General Engineering