Abstract
Two alternate definitions of group averaged diffusion coefficients given in terms of transport mean free paths are equated with upper and lower limits. Thus, the diffusion of the neutron flux in a reactor may be calculated for practical applications whereby in the past the flux could only be correctly calculated for flux separable in space and energy. With the limits it is possible to form a group cross-section library of average transport mean free paths for use in various calculations. (N.W.R.)
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