Neutron angular flux reconstruction in slab geometry using multigroup discrete ordinates transport models

Authors

DOI:

https://doi.org/10.15392/bjrs.v8i3A.1429

Keywords:

, neutron transport theory, discrete Ordinate method, angular reconstruction methodology

Abstract

In this article, we present an application of the coarse-mesh Deterministic Spectral Method (SDM) to generate multigroup angular fluxes in one-dimensional spatial domains using the neutron transport stationary equation, in the formulation of discrete ordinates (SN), considering isotropic scattering source. After obtaining the analytical solution of the SN equations, we replace the integral term of the scattering source in the original neutron transport equation. Thus, we obtain analytically two expressions for angular fluxes in the multigroup formulation, considering the neutron propagation in the positive ( ) and negative ( ) directions, presenting a meaningful reduction in the computational time of simulations of typical neutron shielding problems.

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References

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Published

2021-02-09 — Updated on 2023-01-24

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How to Cite

Balbina, F. T. C. S., Barros, R. C., & Alves Filho, H. (2023). Neutron angular flux reconstruction in slab geometry using multigroup discrete ordinates transport models. Brazilian Journal of Radiation Sciences, 8(3A (Suppl.), 01–18. https://doi.org/10.15392/bjrs.v8i3A.1429 (Original work published February 9, 2021)

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Section

XXI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XXI ENFIR) and VI ENIN