Please use this identifier to cite or link to this item: https://apo.ansto.gov.au/dspace/handle/10238/549
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dc.contributor.authorMcGregor, BJen_AU
dc.date.accessioned2007-11-22T04:24:33Zen_AU
dc.date.accessioned2010-04-30T04:36:26Z-
dc.date.available2007-11-22T04:24:33Zen_AU
dc.date.available2010-04-30T04:36:26Z-
dc.date.issued1975-01en_AU
dc.identifier.citationMcGregor, B. (1975). Comparison of calculations of a reflected reactor with diffusion, sn and monte carlo codes (AAEC/E342). Lucas Heights, NSW: Australian Atomic Energy Commission.-
dc.identifier.govdoc559-
dc.identifier.isbn0642996733en_AU
dc.identifier.otherAAEC-E-343en_AU
dc.identifier.urihttp://apo.ansto.gov.au/dspace/handle/10238/549en_AU
dc.description.abstractA diffusion theory code, POW, was compared with a Monte Carlo transport theory code, KENO, for the calculation of a small C/235U cylindrical core with a graphite reflector. The calculated multiplication factors were in good agreement but differences were noted in region-averaged group fluxes. A one-dimensional spherical geometry was devised to approximate cylindrical geometry. Differences similar to those already observed were noted when the region-averaged fluxes from a diffusion theory (POW) calculation were compared with an SN transport theory (ANAUSN) calculation for the spherical model. Calculations made with SN and Monte Carlo transport codes were in good agreement. It was concluded that observed flux differences were attributable to the POW code, and were not inconsistent with inherent diffusion theory approximations.en_AU
dc.language.isoen_auen_AU
dc.publisherAustralian Atomic Energy Commissionen_AU
dc.subjectComparative evaluations-
dc.subjectNeutron diffusion equation-
dc.subjectNeutron flux-
dc.subjectCarbon-
dc.subjectMultigroup theory-
dc.titleComparison of calculations of a reflected reactor with diffusion, sn and monte carlo codes.en_AU
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