Neutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for Monte Carlo applications.

dc.contributor.authorThompson, JJen_AU
dc.date.accessioned2007-11-22T04:14:00Zen_AU
dc.date.accessioned2010-04-30T04:28:25Zen_AU
dc.date.available2007-11-22T04:14:00Zen_AU
dc.date.available2010-04-30T04:28:25Zen_AU
dc.date.issued1961-07en_AU
dc.description.abstractProbability 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.citationThompson, 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.govdoc117en_AU
dc.identifier.otherAAEC-E-66en_AU
dc.identifier.placeofpublicationLucas Heights, New South Walesen_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/168en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectNeutron diffusion equationen_AU
dc.subjectHomogeneous reactorsen_AU
dc.subjectMonte Carlo Methoden_AU
dc.subjectReactor coresen_AU
dc.titleNeutron diffusion formulae for homogeneous, axially symmetric, anisotropic media, for Monte Carlo applications.en_AU
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