Comparison of calculations of a reflected reactor with diffusion, sn and monte carlo codes
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Date
1975-01
Authors
Journal Title
Journal ISSN
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Publisher
Australian Atomic Energy Commission
Abstract
A 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.
Description
Keywords
Comparative evaluations, Neutron diffusion equation, Neutron flux, Carbon, Multigroup theory
Citation
McGregor, 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.