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The Multi-Group Neutron Diffusion Equation in General Geometries Using the Parseval Identity

  • J. C. L. FernandesEmail author
  • F. Oliveira
  • B. E. J. Bodmann
  • M. T. B. Vilhena
Conference paper

Abstract

Multi-group neutron diffusion equation is still one of the most frequently employed equations for nuclear reactor neutronics calculations, although its limitations are well known. The equation is obtained under the assumptions that scattering is isotropic in the laboratory coordinate system and the region of interest is considered piecewise homogeneous, so that the diffusion coefficients are invariant under spatial transforms like translation and others. It is well known, that such a derivation of diffusion theory rests on certain assumptions, i.e. the flux being sufficiently smooth especially by virtue of neutron absorption or production, which is reasonable since the mean free path is typically larger than the dimensions of the fuel cell and moderator space geometry. The solution of the diffusion equation system is obtained by Parseval relation for different kinds of geometry, where fluctuations (higher moments) are neglected. Further, the continuous energy distribution of neutrons is reduced by the use of two energy groups and the results was compared to literature

Keywords

Diffusion Equation Neutron Problem Parseval Relation Integral Transform General Geometries. 

References

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    Bodmann, B.E.J., Vilhena, M.T., Ferreira, L.S., Bardaji, J.B.: An analytical solver for the multi-group two dimensional neutron-diffusion equation by integral transform techniques. Il Nuovo Cimento della Societ Italiana di Fisica, C 33, 1–10 (2010).Google Scholar
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    Fernandes, J.C.L., Bodmann, B.E.J., Vilhena, M.T.: A Novel to Approach to The Hankel Transform Inversion of the Neutron Diffusion Problem Using Parseval Identity Integral Methods in Science and Engineering, Birkhauser, 105–114, (2012).Google Scholar
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    Sneddon, I.A.: The use of integral transforms. McGraw-Hill, New York (1972).Google Scholar
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    Fernandes, J.C.L.: Solução Analítica da equação de difusão de nêutrons multi-grupo em cilindro infinito homogêneo através da transformada de Hankel, PhD Tesis, UFRGS, Porto Alegre, Brazil (2011).Google Scholar

Copyright information

© Springer International Publishing Switzerland 2015

Authors and Affiliations

  • J. C. L. Fernandes
    • 1
    Email author
  • F. Oliveira
    • 1
  • B. E. J. Bodmann
    • 1
  • M. T. B. Vilhena
    • 1
  1. 1.Federal University of Rio Grande do SulPorto AlegreBrazil

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