Determination of critical experiment correlations for experiments involving highly enriched uranium solutions

Quantifying the correlations among critical experiments has become a topic of interest over the last 10–15 years. The correlations arise from the shared use of fissile material, nonfissile materials, fixtures, and procedures in multiple experiments or multiple experiment series. A Monte Carlo sampling technique proposed as a viable technical method to evaluate these correlations has been implemented within the SCALE 6.2 Sampler sequence. This paper presents the investigation of the use of this new tool and technique for highly enriched uranium solution experiments. One of the first attempts to quantify the correlations among critical experiments examined a series of highly enriched solution experiments, including the HST-001 series. These correlations are included in the International Criticality Safety Benchmark Evaluation Project Handbook, and they form a basis for methodology comparisons. Results generated using the Sampler implementation are compared with these previously published results. Additional studies involving the HST-001 experiment series are also presented. A range of different assumptions of the independence of the geometry components, enrichments, and other material compositions are implemented to investigate the impact of these assumptions on the correlation coefficients. These effects are investigated with these experiments because the calculation time is shorter for the solution experiments than for the low-enriched lattice experiments discussed in a companion paper. The magnitude of the effects of different independence assumptions on the correlation coefficients is important to establish which parameters must be clearly identified as shared or unique for accurate correlation determinations.