Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates Formulation

In this work, we present the most recent numerical results in a nodal approach, which resulted in the development of a new numerical spectral nodal method, based on the spectral analysis of the multigroup, isotropic scattering neutron transport equations in the discrete ordinates ($S_N$) formulation...

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Main Authors: Amaury Munoz Oliva, Hermes Alves Filho
Format: Article
Language:English
Published: Universidade Federal do Rio Grande 2021-11-01
Series:Vetor
Subjects:
Online Access:https://periodicos.furg.br/vetor/article/view/13472
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author Amaury Munoz Oliva
Hermes Alves Filho
author_facet Amaury Munoz Oliva
Hermes Alves Filho
author_sort Amaury Munoz Oliva
collection DOAJ
description In this work, we present the most recent numerical results in a nodal approach, which resulted in the development of a new numerical spectral nodal method, based on the spectral analysis of the multigroup, isotropic scattering neutron transport equations in the discrete ordinates ($S_N$) formulation for fixed-source calculations in non-multiplying media (shielding problems). The numerical results refer to simulations of typical problems from the reactor physics field, in rectangular two-dimensional Cartesian geometry, $X, Y$ geometry, and are compared with the traditional Diamond Difference ($DD$) fine-mesh method results, used as a reference, and the spectral coarse-mesh method Green's function ($SGF$) results.
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spelling doaj.art-be84332e81dc4f8984ca14a7256d45132022-12-22T04:24:49ZengUniversidade Federal do Rio GrandeVetor0102-73522358-34522021-11-01311Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates FormulationAmaury Munoz OlivaHermes Alves Filho0Instituto Politécnico, Universidade do Estado do Rio de Janeiro, IPRJ / UERJIn this work, we present the most recent numerical results in a nodal approach, which resulted in the development of a new numerical spectral nodal method, based on the spectral analysis of the multigroup, isotropic scattering neutron transport equations in the discrete ordinates ($S_N$) formulation for fixed-source calculations in non-multiplying media (shielding problems). The numerical results refer to simulations of typical problems from the reactor physics field, in rectangular two-dimensional Cartesian geometry, $X, Y$ geometry, and are compared with the traditional Diamond Difference ($DD$) fine-mesh method results, used as a reference, and the spectral coarse-mesh method Green's function ($SGF$) results.https://periodicos.furg.br/vetor/article/view/13472Neutron Transport TheoryShielding CalculationsSpectral Nodal Method
spellingShingle Amaury Munoz Oliva
Hermes Alves Filho
Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates Formulation
Vetor
Neutron Transport Theory
Shielding Calculations
Spectral Nodal Method
title Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates Formulation
title_full Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates Formulation
title_fullStr Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates Formulation
title_full_unstemmed Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates Formulation
title_short Spectral-Nodal Deterministic Methodology for Neutron Shielding Calculations using the X, Y - geometry Multigroup Transport Equation in the Discrete Ordinates Formulation
title_sort spectral nodal deterministic methodology for neutron shielding calculations using the x y geometry multigroup transport equation in the discrete ordinates formulation
topic Neutron Transport Theory
Shielding Calculations
Spectral Nodal Method
url https://periodicos.furg.br/vetor/article/view/13472
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