Additional verification of the MCU-BR software package is examined. This is mainly concerned with the computational analysis of the neutron flux density distribution in layers of steel and lead reflectors. Precision computational models of experiments for the assemblies BFS-64, -66, and -80 of the BFS-2 stand were formed and calculations of the critical state, the distribution of the spatial rate of fission reactions of 235U, 238U, and 239Pu, spectral indices, and reactivity effects were performed. The main calculated parameters are in agreement with the experimental values within the measurement error. The results will make it possible to refine the errors and improve and supplement the verification base and will be used to calculate the core characteristics of a lead-cooled fast reactor.
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References
O. N. Andrianova, Zh. V. Borovskaya, G. M. Zherdev, et al., “Precision calculations of experiments on the passage of neutrons through the layers of the reflector on the BFS stands for replenishment of the verification base for substantiating a lead-cooled reactor,” Izv. Vyssh. Uchebn. Zaved. Yad. Fiz., No. 3, 125–133 (2020).
S. V. Zabrodskaya, A. V. Ignatyuk, V. N. Koshcheev, et al., “ROSFOND – Russian National Library of Evaluated Neutron Data,” Vopr. At. Nauki Tekhn. Ser. Yad. Konst., No. 1–2, 3–21 (2007).
M. Chadwick, M. Herman, P. Oblozinskii, et al., “ENDF/BVII.1 nuclear data for science and technology: cross sections, covariances, fission product yields and decay data,” Nucl. Data Sheets, 112, No. 12, 2887–2996 (2011).
K. Shibata, O. Iwamoto, T. Nakagawa, et al., “JENDL-4.0: a new library for nuclear science and engineering,” Nucl. Sci. Technol., 48, No. 1, 1–30 (2011).
A. V. Balovnev, V. K. Davydov, E. O. Soldatov, et al., “A system of codes for the physical design of a lead-cooled fast-neutron reactor,” Vopr. At. Nauki Tekhn. Ser. Yad.-Reakt. Konst., No. 3, 30–36 (2020).
The NJOY Nuclear Data Processing System. User Manual, LA-9303 (1981), Vol. 1.
A. L. Kochetkov, I. P. Matveenko, M. Yu. Semenov, et al., “Critical experiments on the BFS-2 stand in support of the placement of MOX fuel in BN reactors,” Izv. Vyssh. Uchebn. Zaved. Yad. Energet., No. 2, 16–27 (2007).
E. F. Mitenkova and N. V. Novikov, “Features of neutronics calculations of sodium-cooled fast reactors with mixed oxide fuel,” At. Energ., 109, No. 5, 253–262 (2010).
A. A. Blyskavka, A. V. Moiseev, M. Yu. Semenov, et al., “Analysis of the accuracy of the calculation of the energy-release field distribution in the BN-600,” At. Energ., 108, No. 2, 63–70 (2010).
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Translated from Atomnaya Énergiya, Vol. 130, No. 5, pp. 243–249, May, 2021.
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Borovskaya, Z.V., Zhirnov, A.P., Kalugina, K.M. et al. MCU-BR Software Verification by Critical BFS-2 Stand Experiments. At Energy 130, 255–261 (2021). https://doi.org/10.1007/s10512-021-00805-9
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DOI: https://doi.org/10.1007/s10512-021-00805-9