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Integral Neutron Transport and New Computational Methods: A Review

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Integral Methods in Science and Engineering

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Abstract

The neutron transport equation is the basis for the physical simulation of nuclear reactors and, in particular, for nuclear reactor core design. The present work considers the neutron transport equation in integral form, which proves very useful to highlight many interesting physical aspects of the phenomenon and also for practical applications. The basics of integral transport theory are reviewed in the first part of the work. Afterwards, the spatial second-order AN method is derived, illustrating the advantageous features of the model, and two approaches for the numerical solution of the equations are presented. Some numerical examples show the effectiveness and flexibility of the algorithms proposed.

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Acknowledgements

One of the authors (P.R.) is very grateful to the organizers of the IMSE-2012 Conference for the kind invitation and the generous support that enabled him to travel to Bento Gonçalves and to take part in the stimulating scientific sessions held in such a friendly atmosphere.

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Authors and Affiliations

  1. Energy Department, Politecnico di Torino, 24, C.so Duca degli Abruzzi, I-10129, Torino, Italy

    A. Barbarino, S. Dulla & P. Ravetto

Authors
  1. A. Barbarino
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  2. S. Dulla
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  3. P. Ravetto
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Corresponding author

Correspondence to P. Ravetto .

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Editors and Affiliations

  1. Department of Mathematics, The University of Tulsa, Tulsa, USA

    Christian Constanda

  2. Mechanical Engineering, Federal University of Rio Grande do Sul, Porto Alegre, Brazil

    Bardo E.J. Bodmann

  3. LAC, National Institute for Space Research, Sao Jose dos Campos, SĂŁo Paulo, Brazil

    Haroldo F. de Campos Velho

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Barbarino, A., Dulla, S., Ravetto, P. (2013). Integral Neutron Transport and New Computational Methods: A Review. In: Constanda, C., Bodmann, B., Velho, H. (eds) Integral Methods in Science and Engineering. Birkhäuser, New York, NY. https://doi.org/10.1007/978-1-4614-7828-7_3

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