Multi-Group Neutron Propagation in Transport Theory by Space Asymptotic Methods

J. C. L. Fernandes (), S. Dulla (), P. Ravetto () and M. T. B. Vilhena ()
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J. C. L. Fernandes: Federal University of Rio Grande do Sul
S. Dulla: Politecnico di Torino
P. Ravetto: Politecnico di Torino
M. T. B. Vilhena: Federal University of Rio Grande do Sul

Chapter Chapter 19 in Integral Methods in Science and Engineering, 2015, pp 223-234 from Springer

Abstract: Abstract The study of the neutronic response to a localized pulsed source requires accurate models, due to the strong spatial effects coming into play associated with the wavefront propagation. Furthermore, usually neutron sources inject particles at high energy and, consequently, important spectral effects may come into play. In previous works, the propagation phenomenon has been investigated for idealized configurations in exact transport (Dulla et al., Annals of Nuclear Energy C 33:932–940, 2006), restricting the analysis to one-group problems. Furthermore, the numerical effects associated with the application of discrete ordinate and spherical harmonics methods have been analyzed (Dulla and Ravetto, Transactions of the American Nuclear Society C 90:278–280, 2004; Annals of Nuclear Energy C 35:656–664, 2008), illustrating the appearance of time-dependent ray effects.

Keywords: Transport Equation; Integral Transforms; Neutron Transport; Asymptotic Method; Pulsed Sources; Applied Math in Nuclear Reactors (search for similar items in EconPapers)
Date: 2015
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DOI: 10.1007/978-3-319-16727-5_19

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