Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for Monte Carlo applications.
dc.contributor.author | Thompson, JJ | en_AU |
dc.date.accessioned | 2007-11-22T04:14:00Z | en_AU |
dc.date.accessioned | 2010-04-30T04:28:25Z | en_AU |
dc.date.available | 2007-11-22T04:14:00Z | en_AU |
dc.date.available | 2010-04-30T04:28:25Z | en_AU |
dc.date.issued | 1961-07 | en_AU |
dc.description.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. | en_AU |
dc.identifier.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. | en_AU |
dc.identifier.govdoc | 117 | en_AU |
dc.identifier.other | AAEC-E-66 | en_AU |
dc.identifier.placeofpublication | Lucas Heights, New South Wales | en_AU |
dc.identifier.uri | http://apo.ansto.gov.au/dspace/handle/10238/168 | en_AU |
dc.language.iso | en_au | en_AU |
dc.publisher | Australian Atomic Energy Commission | en_AU |
dc.subject | Neutron diffusion equation | en_AU |
dc.subject | Homogeneous reactors | en_AU |
dc.subject | Monte Carlo Method | en_AU |
dc.subject | Reactor cores | en_AU |
dc.title | Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for Monte Carlo applications. | en_AU |
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