Abstract
Several finite element formulations of nodal schemes for neutron diffusion problems are presented: They include nonconforming formulations as well as mixed and mixed-hybrid ones, with exact or approximate evaluation of the matrix coefficients. These different formulations are compared to one another and also related to well-known point- and mesh-centered finite difference schemes. Some numerical results are given in one and two dimensions with different schemes. Applications to two-dimensional neutron transport problems are also proposed through the general approach of transverse integration.
| Original language | English |
|---|---|
| Pages (from-to) | 204-211 |
| Number of pages | 8 |
| Journal | Nuclear Science and Engineering |
| Volume | 92 |
| Issue number | 2 |
| DOIs | |
| State | Published - 1986 |