Abstract

Experiments carried out in the third gas-cooled fast breeder reactor (GCFR) benchmark critical assembly on the Zero Power Reactor-9 at Argonne National Laboratory were analyzed using methods and computer codes employed routinely for design and performance evaluations on power-plant GCFR cores. The program for the Phase III GCFR assembly, with a 1900-liter, three-enrichment zone core, included measurements of reaction-rate profiles in a typical power-flattened design, studies of material reactivity coefficients, reaction ratio and breeding parameter determinations, and comparison of pin with plate fuel loadings. Calculated parameters to compare with all of the measured results were obtained using 10-group cross sections based on ENDF/B-4 and two-dimensional diffusion theory, with adjustments for fuel-cell heterogeneity and void-lattice streaming effects.

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