Abstract
NRC Kurchatov Institute's critical facility performed a series of experiments to study neutron characteristics of water-uranium compositions that contains fuel pins with uranium enriched up to 6.5 wt% of U-235 and erbium oxide (Er2O3) absorbers. Sizes, shapes, and compositions were defined to model uranium-erbium fuel considered for VVER extended fuel cycles. We believe the experimental results are valid for verifying and validating the computer codes employed to research and design advanced fuel cycles. The paper describes the main implemented fuel compositions and presents experimental results for criticality parameters and neutron flux distributions.The Monte Carlo code MCU-PD and the spectral code TVS-M were applied for the computational analysis. Both of these codes are used for VVER fuel cycles design. Results of the calculations of the primary neutron characteristics are compared to the experimental values.
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