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Applying the UNK Complex to Calculate Elementary Cells Featuring Heterogeneous Vertical Fuel Distribution

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Abstract

Algorithms are introduced to calculate the first-flight neutron collision probability (FFCP) matrices in 3D geometry. The same algorithms are used to calculate the cell temperature field in R–Z geometry. These codes are part of the UNK complex. The results of applying these programs to calculate the change in nuclide composition and the neutron breeding ratio during fuel burnup are given for homogeneous and heterogeneous vertical fuel distribution in fuel rods.

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Funding

This study was supported by the Russian Foundation for Basic Research (RFBR) within the scope of research project no. 19-29-02015.

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Authors and Affiliations

  1. National Research Center Kurchatov Institute, 123182, Moscow, Russia

    V. Yu. Blandinskiy, E. A. Bobrov, O. V. Davidenko, T. Yu. Karpushkin, A. A. Polunovskiy & S. V. Tsibulskiy

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  1. V. Yu. Blandinskiy
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  2. E. A. Bobrov
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  3. O. V. Davidenko
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  4. T. Yu. Karpushkin
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  5. A. A. Polunovskiy
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  6. S. V. Tsibulskiy
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Corresponding author

Correspondence to T. Yu. Karpushkin.

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The authors declare that they have no conflicts of interest.

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Translated by V. Vetrov

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Blandinskiy, V.Y., Bobrov, E.A., Davidenko, O.V. et al. Applying the UNK Complex to Calculate Elementary Cells Featuring Heterogeneous Vertical Fuel Distribution. Phys. Atom. Nuclei 85, 1439–1443 (2022). https://doi.org/10.1134/S1063778822080129

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  • DOI: https://doi.org/10.1134/S1063778822080129

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