Methodological program techniques for performing neutron-physical calculations of fast-reactor cores with a description of the main codes TRIGEX, JARFR, GEFEST, MMKKENO, and ModExSys are described. The results of verification and assessment of the methodological errors on the basis of a test model of BN-600 are presented. Transport effects and mesh errors in the reaction rate distributions in the core, lateral screen, and in-reactor storage area are evaluated. An integral assessment of the computational accuracy is performed by comparing with the experimental data obtained by γ-scans of BN-600 fuel assemblies. It is shown that calculations describe the experimental data over the core with an error no worse than 5%. In the lateral screen and the in-reactor storage area, the discrepancy between the calculations and experiment does not exceed 20–30%.
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Translated from Atomnaya Énergiya,Vol. 108, No. 2, pp. 63–70, February, 2010.
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Blyskavka, A.A., Moiseev, A.V., Semenov, M.Y. et al. Accuracy analysis of BN-600 power density calculations. At Energy 108, 79–88 (2010). https://doi.org/10.1007/s10512-010-9260-9
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DOI: https://doi.org/10.1007/s10512-010-9260-9