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The spectral nodal method applied to multigroup [formula omitted] neutron transport problems in One-Dimensional geometry with Fixed–Source.

Authors :
Oliva, Amaury Muñoz
Filho, Hermes Alves
Martins e Silva, Davi José
García Hernández, Carlos Rafael
Source :
Progress in Nuclear Energy. May2018, Vol. 105, p106-113. 8p.
Publication Year :
2018

Abstract

The nodal methods, as deterministic models, form a class of numerical methods developed to generate accurate numerical solutions of the Boltzmann equation for neutron transport. These methods are algebraically and computationally more laborious than the traditional deterministic fine-mesh methods like the Diamond Difference method ( D D ). However, their numerical solution for traditional coarse-mesh problems is more accurate. For this reason, the nodal methods and their algorithms for direct and iterative solution schemes have been the subject of extensive research. In this paper we propose a simpler methodology for the development of a method of spectral nodal class which is tested as an initial study of the solutions (spectral analysis) of the neutron transport equation in the formulation of discrete ordinates ( S N ), in one-dimensional geometry, multigroup energy approximation, isotropic scattering and considering homogeneous and heterogeneous domains. These results are compared with the traditional fine-mesh D D method and the spectral nodal methods, spectral Green's function ( S G F ) and Response Matrix ( R M ) to test their numerical accuracy, stability and consistency. [ABSTRACT FROM AUTHOR]

Details

Language :
English
ISSN :
01491970
Volume :
105
Database :
Academic Search Index
Journal :
Progress in Nuclear Energy
Publication Type :
Academic Journal
Accession number :
128395480
Full Text :
https://doi.org/10.1016/j.pnucene.2017.12.017