Nuclear Science and Engineering / Volume 1 / Number 4 / August 1956 / Pages 268-279
Technical Paper / dx.doi.org/10.13182/NSE56-A18602
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The neutron distribution in the moderator of an infinite square-lattice array is found assuming diffusion theory and a uniform production of neutrons throughout the moderator. Variation of neutron flux density along the sides of a lattice cell is shown to be significant. Nevertheless, the thermal utilization of the lattice can be quite accurately calculated by the use of a “cylindricalized” cell.