Integral Neutron Transport and New Computational Methods: A Review

A. Barbarino (), S. Dulla () and P. Ravetto ()
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A. Barbarino: Politecnico di Torino, Energy Department
S. Dulla: Politecnico di Torino, Energy Department
P. Ravetto: Politecnico di Torino, Energy Department

Chapter Chapter 3 in Integral Methods in Science and Engineering, 2013, pp 41-56 from Springer

Abstract: 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.

Keywords: Neutron transport; Integral transport equation; AN method; Boundary element method; Spectral element method; Nuclear reactor physics (search for similar items in EconPapers)
Date: 2013
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DOI: 10.1007/978-1-4614-7828-7_3

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