A modified power method for the multilayer multigroup two-dimensional neutron diffusion equation
Author:
Funder
CAPES
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
Reference8 articles.
1. Resolution of the Generalized Eigenvalue Problem in the Neutron Diffusion Equation Discretized by the Finite Volume Method;Bernal,2014
2. On the neutron multi-group kinetic diffusion equation in a heterogeneous slab: an exact solution on a finite set of discrete points;Ceolin;Ann. Nucl. Energy,2015
3. Nuclear Reactor Analysis;Duderstadt,1976
4. Analytic solution for two-group diffusion equations in a multilayered slab using laplace transform technique;Lemos;Prog. Nucl. Energy,2008
5. A galerkin approach to the boundary element-response matrix method for the multigroup neutron diffusion equations;Maiani;Ann. Nucl. Energy,2004
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