Spectral Nodal Methodology for Multigroup Slab-Geometry Discrete Ordinates Neutron Transport Problems with Linearly Anisotropic Scattering
DOI:
https://doi.org/10.15392/bjrs.v8i3B.618Keywords:
Neutron Transport Equation, Discrete Ordinates Method, Nodal Methods, Anisotropic Scattering, Computational Modeling.Abstract
In this paper, we propose a numerical methodology for the development of a method of the spectral nodal class that generates numerical solutions free from spatial truncation errors. This method, denominated Spectral Deterministic Method (SDM), is tested as a study of the solutions (spectral analysis) of neutron transport equations in the discrete ordinates (SN) formulation, in slab geometry, multigroup approximation, with linearly anisotropic scattering, considering a heterogeneous domain with fixed-source. The unknowns in the methodology are the cell-edge, and cell average angular fluxes, the numerical values calculated for these quantities coincide with the analytic solution of the equations. These numerical results are shown and compared with the traditional fine-mesh Diamond Difference (DD) method and the coarse-mesh spectral Green's function (SGF) method to illustrate the method's accuracy and stability. The solution algorithms problem is implemented in a computer simulator made in C++ language, the same that was used to generate the results of the reference work.
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References
Lewis E.E., Miller W. F., Computational methods of neutron transport, American Nuclear Society, Illinois, USA ,1993.
Duderstadt J.J., Hamilton L.J., Nuclear Reactor Analysis, John Wiley & Sons, New York, 1976.
Barros R.C., A Spectral Nodal Method for the Solution of Discrete Ordinates Problems in one and two-Dimensional Cartesian Geometry. Ph.D. dissertation, The University of Michigan, Ann Arbor, Michigan, 1990.
Barros R.C., Larsen E.W., A Numerical Method for One-Group Slab-Geometry Discrete Ordi-nates Problems with no Spatial Truncation Error, Nuclear Science and Engineering, v.104, p. 199-208, 1990.
Oliva A. M. H., Alves Filho H., Silva D.J., Garcia Hernandez C.R, Computer Deterministic Mod-elling of Nuclear Problems using Nodal Methods", Proceeding Series of the Brazilian Society of Applied and Computational Mathematics, Gramado - RS, September 5th to 9th, 2016, v. 5, 2017.
Garcia R. D. M., Siewert C. E., Multigroup Transport Theory with Anisotropic Scattering", Jour-nal of Computational Physics, v.46, p. 237-270, 1982.
Garcia R. D. M, Siewert C. E., Multislab Multigroup Transport Theory with L th Order Aniso-tropic Scattering", Journal of Computational Physics, v.50, p. 181-192, 1983.
Menezes W.A., Métodos espectronodais para cálculos de transporte de partículas neutras com fonte fixa na formulação de ordenadas discretas e multigrupo de energia. Ms.C. dissertation, Uni-versidade do Estado do Rio de Janeiro, Nova Friburgo, RJ, 2012.
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