From transport to diffusion through a space asymptotic approach

S. Dulla, S. Canepa and P. Ravetto

Mathematics and Computers in Simulation (MATCOM), 2010, vol. 80, issue 11, 2134-2141

Abstract: The spatially asymptotic theory is a useful approach to the neutron transport model for nuclear reactor physics applications. For steady-state problems the transport equation is taken in an infinite medium and it is treated by the Fourier transform. A formal solution is thus obtained for any assumption on the order of anisotropy, leading to the BN formulation. In the case of isotropic emissions the Green function of the problem can be given an explicit expression by the inverse Fourier transformation, leading to the solution that can also be obtained by Case method.

Keywords: Neutron transport; Neutron diffusion; Space asymptotic theory (search for similar items in EconPapers)
Date: 2010
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Persistent link: https://EconPapers.repec.org/RePEc:eee:matcom:v:80:y:2010:i:11:p:2134-2141

DOI: 10.1016/j.matcom.2010.04.007

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