A modified power method for the multilayer multigroup two-dimensional neutron diffusion equation

In this work we present a methodology of solution of the multigroup multi-layer stationary neutron diffusion equation in two-dimensional cartesian geometry. This eigenvalue problem describes the criticality of nuclear reactor, that is, it establishes the ratio between the numbers of neutrons generat...

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Detalhes bibliográficos
Autor principal: Zanette, Rodrigo (author)
Outros Autores: Petersen, Claudio Zen (author), Schramm, Marcelo (author), Zabadal, Jorge Rodolfo Silva (author)
Formato: other article
Idioma:eng
Publicado em: 2021
Assuntos:
Texto completo:http://hdl.handle.net/10183/222117
País:Brasil
Oai:oai:www.lume.ufrgs.br:10183/222117