Features and capabilities of the SUN BPSD module for assessing the error in fuel burnup calculations due to the uncertainty of nuclear data and reactor plant process parameters, as well as fuel irradiation conditions, are described. Using the SUN module, two different methods for estimating the uncertainty of irradiated fuel characteristics were implemented. The post-reactor studies of fuel rods irradiated in a BN-350 reactor with mixed uranium-plutonium oxide fuel were considered as a demonstration calculation test using the SUN module.
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References
G. N. Manturov, Methodical, Constant, and Software Assurance for the Neutron-Physical Calculations of Fast Reactors and Estimates of Errors in Calculated Forecasts: Diss. Cand. Sci. (Engineering), NRC Kurchatov Institute, Moscow (2017).
E. F. Seleznev, A. A. Belov, V. I. Belousov, and I. S. Chernova, “Modernization of the BPSD software for calculating the problems of nuclide kinetics,” Izv. Vuzov. Yad. Energet., Iss. 4, 115–127 (2018).
A. A. Belov, M. V. Kryachko, and O. I. Chertovskikh, “Calculation of the experiment on the irradiation of structural materials in a fl ux of thermonuclear neutrons by the BPSD burnup code,” Vopr. At. Nauki Tekhn. Ser. Yad.-Reakt. Konst., No. 4, 47–62 (2021).
V. B. Glebov, G. G. Kulikov, V. V. Khromov, et al., “Calculating the sensitivity of reactor characteristics to constants, taking into account the variations in the nuclide composition of the reactor during the campaign,” Vopr. At. Nauki Tekhn. Ser. Yad.-Reakt. Konst., No. 1, 11–17 (1991).
C. Diez, O. Cabellos, D. Rochman, et al., “Monte Carlo uncertainty propagation approaches in ADS burn-up calculations,” Ann. Nucl. Energy, 54, 27–35 (2013).
O. N. Andrianova, “Methodological aspects of the error component in the calculations of reactor characteristics due to the resonance structure of neutron cross-sections,” Vopr. At. Nauki Tekhn. Ser. Yad.-Reakt. Konst., No. 1, 74–86 (2017).
R. K. Goncharov, A. V. Zvonarev, V. A. Kolyzhenkov, et al., “Ratios of average cross-sections of some fuel nuclides in the low-enrichment zone and in the uranium-plutonium module of the BN-350 reactor,” At. Energiya, 66, Iss. 5, 353–354 (1989).
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Translated from Atomnaya Énergiya, Vol. 133, No. 5–6, pp. 325–327, November–December, 2022.
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Chertovskikh, O.I., Belov, A.A. & Andrianova, O.N. Uncertainty Assessment and Sensitivity Analysis in the Problems of Nuclide Kinetic Modeling Using the Sun Module of BPSD Software. At Energy 133, 346–349 (2023). https://doi.org/10.1007/s10512-023-01019-x
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DOI: https://doi.org/10.1007/s10512-023-01019-x