Development of a finite volume inter-cell polynomial expansion method for the neutron diffusion equation

@article{Bernal2016DevelopmentOA,
  title={Development of a finite volume inter-cell polynomial expansion method for the neutron diffusion equation},
  author={A. Bernal and J. Rom{\'a}n and R. Mir{\'o} and D. Ginestar and G. Verd{\'u}},
  journal={Journal of Nuclear Science and Technology},
  year={2016},
  volume={53},
  pages={1212 - 1223}
}
  • A. Bernal, J. Román, +2 authors G. Verdú
  • Published 2016
  • Physics
  • Journal of Nuclear Science and Technology
  • Heterogeneous nuclear reactors require numerical methods to solve the neutron diffusion equation (NDE) to obtain the neutron flux distribution inside them, by discretizing the heterogeneous geometry in a set of homogeneous regions. This discretization requires additional equations at the inner faces of two adjacent cells: neutron flux and current continuity, which imply an excess of equations. The finite volume method (FVM) is suitable to be applied to NDE, because it can be easily applied to… CONTINUE READING
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