On the spectral Green’s function-constant nodal method for fixed-source SN problems in X,Y-geometry with arbitrary L’th-order anisotropic scattering

Authors

  • Welton Menezes Fluminense Federal University
  • Gustavo Alvarez Fluminense Federal University
  • Ricardo Barros Rio de Janeiro State University

DOI:

https://doi.org/10.15392/bjrs.v8i3A.1490

Keywords:

energy multigroup, fixed source, discrete ordinates, anisotropic scattering.

Abstract

Presented here is an extension of the spectral Green’s function-constant nodal (SGF-CN) method for the numerical solution of energy multigroup, fixed-source, discrete ordinates (SN) problems in X, Y-geometry with arbitrary L’th-order of scattering anisotropy, provided L<N. This analytical coarse-mesh method uses the multigroup SGF method for numerically solving the one-dimensional transverse-integrated SN nodal equations with constant approximations for the transverse leakage terms. The only approximations in the present version of the SGF-CN method occur in these transverse leakage terms, as the energy-group transfer scattering source terms are treated analytically within the offered method. Numerical results to typical model problems are given to illustrate the method’s accuracy and to analyze the efficiency of the offered SGF-CN computer code for neutral particle transport calculations.  

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Author Biography

Welton Menezes, Fluminense Federal University

Welton Menezes is a professor at the Exact Sciences Department at the Fluminense Federal University (UFF, Volta Redonda-Rio de Janeiro). He obtained his Doctoral degree in computational modeling from the University of the State of Rio de Janeiro, 2012. His current lines of research are: Computational Neutronics; Direct Shielding Problems and Inverse Problems of Analytical Reconstruction.

References

LEWIS, E, E., MILLER, W. F. Computational methods of neutron transport, 2nd ed. La Grange Park, Illinois: American Nuclear Society, 1993.

WALTERS, W. F.; O'DELL, R. D. A nodal methods for discrete-ordinates transport problems in x,y-geometry. Proceedings of the International Topical Meeting on Advances in Mathematical Methods for the Solution of Nuclear Engineering Problems. vol. 1, Munich: American Nuclear Society, 1981. pp. 115-129.

LAWRENCE, R. D. Progress in nodal methods for the solution of the neutron diffusion and transport equations. Progress in Nuclear Energy, vol. 17, pp. 93-116, 1986.

AZMY, Y. Y. Comparison of three approximations to the linear-linear nodal transport method in weighted diamond-difference form. Nuclear Science and Engineering, pp. 190-200, 1988.

BARROS, R. C.; LARSEN E. W. A numerical method for multigroup slab-geometry discrete ordinates problems with no spatial truncation error. Transport Theory and Statistical Physics, pp. 441 - 462, 1990.

MENEZES, W. A. et al. 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, pp. 66 – 80, 2018.

DOMINGUEZ, D. S.; HERNANDEZ, R.G., BARROS, R. C. Spectral nodal method for numerically solving two-energy group x,y geometry neutron diffusion eigenvalue problems. International Journal of Nuclear Energy Science and Technology, 2010.

BARROS, R. C.; LARSEN E. W. A spectral nodal method for one-Group X,Y-geometry discrete ordinates problems. Nuclear Science and Engineering, pp. 34-45, 1992.

MENEZES W. A.; ALVAREZ G. B.; BARROS R. C. A generalization of the energy multigroup spectral Green's function constant nodal method for fixed-source SN problems in x, y-geometry with arbitrary l'th-order of anisotropic scattering, In: INTERNATIONAL NUCLEAR ATLANTIC CONFERENCE, 2019, Santos. On CD Proceedings.

CACUCI, D. G. Handbook of nuclear engineering, Vol. I: Nuclear Engineering Fundamentals. New York: Springer Science + Business Media LLC, 2010.

Benchmark Problem Committee of the Mathematics and Computation Division of Amer. Nucl. SOC:. Argonne Code Center; Benchmark problem book, numerical determination of the space, time, angle or energy distribution of particles in an assembly, ANL-7416, 1972.

ROY, R. Anisotropic scattering for integral transport codes. Part 2. Cyclic tracking and its application to xy lattices. Annals of Nuclear Energy, pp. 511-524, 1991.

YAMAMOTO, A. et al. Simplified treatments of anisotropic scattering in LWR core calculations. Journal of Nuclear Science and Technology, pp. 217-229, 2008.

MELLO, J. M.; BARROS, R. C. An exponential spectral nodal method for one-speed x,y-geometry deep penetration discrete ordinates problems". Annals of Nuclear Energy, pp. 1855 - 1869, 2002.

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, pp. 958 - 966, 2007.

ANLI, F.; GÜNGÖR, S. A spectral nodal method for one-group x,y,z-Cartesian geometry discrete ordinates problems. Annals of Nuclear Energy, pp. 669 - 680, 1996.

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Published

2021-02-09

How to Cite

Menezes, W., Alvarez, G., & Barros, R. (2021). On the spectral Green’s function-constant nodal method for fixed-source SN problems in X,Y-geometry with arbitrary L’th-order anisotropic scattering. Brazilian Journal of Radiation Sciences, 8(3A (Suppl.). https://doi.org/10.15392/bjrs.v8i3A.1490

Issue

Section

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