Please use this identifier to cite or link to this item: https://apo.ansto.gov.au/dspace/handle/10238/168
Title: Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for monte carlo applications.
Authors: Thompson, JJ
Keywords: Neutron diffusion equation
Homogeneous reactors
Monte Carlo method
Reactor cores
Issue Date: Jul-1961
Publisher: Australian Atomic Energy Commission
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.
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.
Gov't Doc #: 117
URI: http://apo.ansto.gov.au/dspace/handle/10238/168
Appears in Collections:Scientific and Technical Reports

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