Edward R. Gotsky, James P. Cusick, Donald Bogart
Two-dimensional two-group diffusion calculations were performed on the NACA reactor simulator in order to evalate the reactivity effects of fuel plates removed successively from the center experimental fuel element of a seven- by three-element core loading at the Oak Ridge Bulk Shielding Facility. The reactivity calculations were performed by two methods: in the first, the slowing-down properties of the experimental fuel element were represented by infinite media parameters; and, in the second, the finite size of the experimental fuel element was recognized, and the slowing-down properties of the surrounding core were attributed to this small region. The two calculation methods agreed reasonably well with the experimental reactivity effects.
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