Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method

Analytical solution of the multigroup neutron diffusion equation coupled with an iterative method

Many numerical methods are being used to solve the multigroup neutron diffusion equation for different types of nuclear reactors. These methods solve this equation quite accurately and determine the neutron flux and power distribution in the reactor as well as the eigenvalue of the reactor core. In...

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Bibliographic Details
Main Authors: Adilson Costa da Silva, Aquilino Martinez, Rodrigo Diniz, Alessandro Gonçalves
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2022-10-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
neutron diffusion equation
analytical solution
iterative method
eigenvalue
slab reactor
Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/2005
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