| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1729332 | Annals of Nuclear Energy | 2017 | 7 Pages |
Abstract
⺠Coupled neutron and gamma transport is considered in the multigroup diffusion approximation. ⺠The model accommodates fission, up- and down-scattering and common neutron-gamma interactions. ⺠The exact solution to the diffusion equation in a heterogeneous media of any number of regions is found. ⺠The solution is shown to parallel the one-group case in a homogeneous medium. ⺠The discussion concludes with a heterogeneous, 2 fuel-plate 93.2% enriched reactor fuel benchmark demonstration.
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Authors
B.D. Ganapol,