Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for Monte Carlo applications.
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Date
1961-07
Authors
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Journal ISSN
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Publisher
Australian Atomic Energy Commission
Abstract
Probability distributions and mean values relating to the diffusion of monoenergetic neutrons in a homogeneous but anisotropic medium are derived as basic studies of Monte Carlo calculations of radial and axial diffusion coefficients in heterogeneous systems. The generalisation of diffusion theory for application to anisotropic media is also discussed.
Description
Keywords
Neutron diffusion equation, Homogeneous reactors, Monte Carlo Method, Reactor cores
Citation
Thompson, J. J. (1961). Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for monte carlo applications. (AAEC/E66). Lucas Heights, N.S.W.: Research Establishment, Australian Atomic Energy Commission.