Home / Store / Journals / Electronic Articles / Nuclear Science and Engineering / Volume 92 / Number 2 / Pages 204-211
E. Del Valle, J. P. Hennart, D. Meade
Nuclear Science and Engineering / Volume 92 / Number 2 / Pages 204-211
Format:electronic copy (download)
Several finite element formulations of nodal schemes for neutron diffusion problems are presented: They include nonconforming primal 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.
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