Solution for the Multigroup Neutron Space Kinetics Equations by Source Iterative Method

Solution for the Multigroup Neutron Space Kinetics Equations by Source Iterative Method

In this work, we used a modified Picard’s method to solve the Multigroup Neutron Space Kinetics Equations (MNSKE) in Cartesian geometry. The method consists in assuming an initial guess for the neutron flux and using it to calculate a fictitious source term in the MNSKE. A new source term is calcula...

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Bibliographic Details
Main Authors: Matheus Gularte Tavares, Claudio Zen Petersen, Marcelo Schramm, Rodrigo Zanette
Format: Article
Language:English
Published: Brazilian Radiation Protection Society (Sociedade Brasileira de Proteção Radiológica, SBPR) 2021-07-01
Series:Brazilian Journal of Radiation Sciences
Subjects:
neutron diffusion equation
source iterative method
laplace transform
stehfest algorithm
polinomial interpola-tion.
Online Access:https://bjrs.org.br/revista/index.php/REVISTA/article/view/731
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