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Original Articles

Recent Advances in Spectral Nodal Methods for Numerically Solving Neutron‐Diffusion Eigenvalue Problems

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Pages 331-346 | Published online: 15 Aug 2006

References

  • Barros , Ricardo C. 1992 . “ Um Método Numérico Livre de Erro de Truncamento Espacial para Cálculos Unidimensionais de Multigrupo Difusão ” . In Proceedings of the IV Congresso Geral de Energia Nuclear Vol. 1 , Rio de Janeiro
  • Barros , Ricardo C. , Filho , Hermes Alves , Orellana , Esbel T. Valero , da Silva , Fernando Carvalho , do Couto , Nozimar , Dominguez , Dany S. and Hernandez , Carlos R. G. 2003 . Progress in Nuclear Energy , 42 ( 4 ) : 385 – 426 .
  • Diaz , O. , Dominguez , D. S. and García , C. 2003 . “ Advances in spectral nodal methods for numerically solving two‐group neutron diffusion equation ” . In Proceedings of the 18th International Conference on Transport Theory Rio de Janeiro
  • Dominguez Dany , S. , Lorenzo , Daniel M. , Hernandez , Carlos G. , Barros , Ricardo C. , do Couto , Nozimarda and da Silva , Fernando C. 2001 . Spectral nodal method for one‐speed X, Y geometry eigenvalue diffusion problems . Proceedings of Computational Heat and Mass Transfer , : Rio de Janeiro
  • Smith , K. S. An Analytic Nodal Method for Solving the Two‐Group, Multidimensional, Static and Transient Neutron Diffusion Equation M.Sc. diss. M.I.T
  • Varga , R. S. 1962 . Matrix Iterative Analysis Englewood Cliffs, NJ : Prentice‐Hall .
  • Weston , Stacey M. 2001 . Nuclear Reactor Physics New York : John Wiley and Sons .

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