Nuclear Science and Engineering / Volume 76 / Number 3 / December 1980 / Pages 263-281
Technical Paper / dx.doi.org/10.13182/NSE80-A21317
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Diffusion theory overestimates neutron transport in voided or low-density regions of a reactor when the diffusion coefficient is defined as 1/3Σtr. Alternative definitions of the diffusion coefficient for such regions have been proposed. The present paper summarizes some definitions of axial diffusion coefficient for cylindrical channels and proposes a modification to an earlier formula. The results of calculations for a channel in a fast reactor supercell model using different formulas are compared and the limitations of this method, which involves changing only the channel diffusion coefficient, are discussed.