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Integral Neutron Transport and New Computational Methods: A Review

In: Integral Methods in Science and Engineering

Author

Listed:
  • A. Barbarino

    (Politecnico di Torino, Energy Department)

  • S. Dulla

    (Politecnico di Torino, Energy Department)

  • P. Ravetto

    (Politecnico di Torino, Energy Department)

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.

Suggested Citation

  • A. Barbarino & S. Dulla & P. Ravetto, 2013. "Integral Neutron Transport and New Computational Methods: A Review," Springer Books, in: Christian Constanda & Bardo E.J. Bodmann & Haroldo F. de Campos Velho (ed.), Integral Methods in Science and Engineering, edition 127, chapter 0, pages 41-56, Springer.
    • Handle: RePEc:spr:sprchp:978-1-4614-7828-7_3
    DOI: 10.1007/978-1-4614-7828-7_3
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