Abstract

For the computational support of innovative projects it is necessary to use high-fidelity codes, which must be verified and validated. In Russia, MCU and SERPENT codes are widely used. The MCU code was previously chosen as the ‘Proryv’ project code. Both of these codes are used for calculation of fast reactors, although they are certified for thermal reactors. Therefore, there is a need to show how accurately they allow calculating the characteristics of fast reactors. For cross-verification of these codes, the main characteristics of the benchmark of BN-600 reactor with a hybrid core were calculated: neutron multiplication factors, reactivity coefficients, distribution of energy release over zones, reaction rates. The values of the neutron multiplication factors for various states of the model obtained with the MCU-PTR are systematically higher than the values obtained with the SERPENT 2 (for majority of the states by 0.4%). The values of the reactivity coefficients have the same sign, however, difference between both codes can reach 160% and if compared with the benchmark – 181%. For the majority of reactivity coefficients this compares with the distribution of the results presented in the benchmark. The MCU results are closer to the benchmark than the Serpent ones.

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