Solution of the Multigroup Neutron Diffusion Eigenvalue Problem in Slab Geometry by Modified Power Method

Solution of the Multigroup Neutron Diffusion Eigenvalue Problem in Slab Geometry by Modified Power Method

We describe in this work the application of the modified power method for solve the multigroup neutron diffusion eigenvalue problem in slab geometry considering two-dimensions for nuclear reactor global calculations. It is well known that criticality calculations can often be best approached by solv...

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Bibliographic Details
Main Authors: Rodrigo Zanette, Claudio Zen Petersen, Matheus Gularte Tavares
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2021-02-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
neutron diffusion equation
eigenvalue problem
modified power method
polynomial interpolation.
Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/624
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