The modified spectral deterministic method applied to fixed–source discrete ordinates problems in X,Y–geometry
DOI:
https://doi.org/10.15392/bjrs.v8i3A.1268Keywords:
deterministic method, discrete ordinates formulation, fixed–source, spectral analysisAbstract
A new approach for the application of the coarse–mesh Modified Spectral Deterministic method to numerically solve the two–dimensional neutron transport equation in the discrete ordinates (Sn) formulation is presented in this work. The method is based on within node general solution of the conventional one–dimensional Sn transverse integrated equations considering constant approximations for the transverse leakage terms and obtaining the Sn spatial balance equations. The discretized equations are solved by using a modified Source Iteration scheme without additional approximations since the average angular fluxes are computed analytically in each iteration. The numerical algorithm of the method presented here is algebraically simpler than other spectral nodal methods in the literature for the type of problems we have considered. Numerical results to two typical model problems are presented to test the accuracy of the offered method.
- Views: 123
- PDF Downloads: 126
Downloads
References
BARROS, R.C.; LARSEN, E.W. A Numerical Method for One–Group Slab–Geometry Discrete Ordinates Problems with No Spatial Truncation Error. Nuclear Science and Engineering, v. 104, p. 199–208, 1990.
MENEZES, W.A.; ALVES FILHO, H.; BARROS, R.C. Spectral Green’s function nodal method for multigroup S_N problems with anisotropic scattering in slab–geometry non–multiplying media. Annals of Nuclear Energy, v. 64, p. 270–275, 2014.
SILVA , D.M.; LYDIA, E.J.; GUIDA, M.R.; ZANI, J.H.; ALVES FILHO, H.; BARROS, R.C. Analytical methods for computational modeling of fixed–source slab–geometry discrete ordinates transport problems: Response matrix and hybrid S_N. Progress in Nuclear Energy, v. 69, p. 77–84, 2013.
BARICHELLO, L.B.; SIEWERT, C.E. A discrete–ordinates solution for a non–grey model with complete frequency redistribution. Journal of Quantitative Spectroscopy and Radiative Transfer, v. 62, p. 665–675, 1999.
DA SILVA, O.P.; GUIDA, M.R.; ALVES FILHO, H.; BARROS, R.C. A response matrix spectral nodal method for energy multigroup X,Y–geometry discrete ordinates problems in non–multiplying media. Progress in Nuclear Energy, v. 125, p. 103288, 2020.
BARROS, R.C.; LARSEN, E.W. A Spectral Nodal Method for One–Group X, Y–Geometry Discrete Ordinates Problems. Nuclear Science and Engineering, v. 111, p. 34–45, 1992.
MENEZES, W.A.; ALVES FILHO, H.; BARROS, R.C. An analytical nodal method for energy multi–group discrete ordinates transport calculations in two–dimensional rectangular geometry. International Journal of Nuclear Energy Science and Technology, v. 12, p. 66–80, 2018.
PICOLOTO, C.B.; DA CUNHA. R.D.; BARROS, R.C.; BARICHELLO, L.B. An analytical approach for solving a nodal formulation of two–dimensional fixed–source neutron transport problems with linearly anisotropic scattering. Progress in Nuclear Energy, v. 98, p. 193–201, 2017.
OLIVA, A.M.; ALVES FILHO, H.; SILVA , D.M.; GARCIA, C.R. The spectral nodal method applied to multigroup S_N neutron transport problems in One–Dimensional geometry with Fixed–Source. Progress in Nuclear Energy, v. 105, p.106–113, 2018.
LEWIS, E.E.; MILLER, W.F. Computational methods of neutron transport, 1st ed., Illinois, USA: American Nuclear Society, 1993.
PRINJA, A.K.; LARSEN, E.W. General principles of neutron transport. In: CACUCI, D.G. Handbook of nuclear engineering, 1st ed., New York, USA: Springer Science + Business Media, 2010. P.427–542.
CURBELO, J.P.; DA SILVA, O.P.; BARROS, R.C. Application of an adjoint technique to one–speed X,Y–geometry source–detector transport problems in the discrete ordinates formulation using a spectral nodal method. Progress in Nuclear Energy, v. 108, p. 445–453, 2018.
LIBOTTE, R.B.; ALVES FILHO, H.; BARROS, R.C. Deterministic numerical method applied to neutron shielding problems using the multigroup transport theory in discrete ordinates formulation. In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, 2019, Santos, SP, Brazil: Associação Brasileira de Energia Nuclear, 2019. p. 4640-4650.
AZMY, Y.Y. Comparison of Three Approximations to the Linear–Linear Nodal Transport Method in Weighted Diamond–Difference Form. Nuclear Science and Engineering, v. 100, p. 190–200, 1988.
DOMINGUEZ, D.S.; BARROS, R.C. The spectral Green’s function linear–nodal method for one–speed X,Y–geometry discrete ordinates deep penetration problems. Annals of Nuclear Energy, v. 34, p. 958–966, 2007.
Published
How to Cite
Issue
Section
License
Copyright (c) 2021 Brazilian Journal of Radiation Sciences
This work is licensed under a Creative Commons Attribution 4.0 International License.
Licensing: The BJRS articles are licensed under a Creative Commons Attribution 4.0 International License, which permits use, sharing, adaptation, distribution and reproduction in any medium or format, as long as you give appropriate credit to the original author(s) and the source, provide a link to the Creative Commons license, and indicate if changes were made. The images or other third party material in this article are included in the article’s Creative Commons license, unless indicated otherwise in a credit line to the material. If material is not included in the article’s Creative Commons license and your intended use is not permitted by statutory regulation or exceeds the permitted use, you will need to obtain permission directly from the copyright holder. To view a copy of this license, visit http://creativecommons.org/licenses/by/4.0/