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KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors

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Abstract

The paper considers the KIR-TG software package, which is designed for the interconnected neutron-physical and thermohydraulic test calculations of the infinite grid of VVER-SKD fuel elements. As part of the work, a software program written in the Python and Lua dynamic programming languages for linking between the module for calculating neutron physics (KIR computer program) and the TK-SKD thermohydraulic module was created and applied. The use of precision calculation performed by the Monte Carlo method in the neutron-physical part avoids the error of deterministic approximation methods in the calculation results. The problem statement, as well as the nature and results of the work, revealed the advantages of this approach to solving problems related to thermal-hydraulic calculations: parallel neutronic and sequential thermal-hydraulic calculations do not affect the overall speed of the associated calculation, the calculation codes are developed in parallel to save time and resources, and errors are tracked separately.

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References

  1. Zborovskii, V.G., Khoruzhiii, O.V., Likhanskii, V.V.: Calculation module for determining the physical parameters of the reactor channel with a supercritical pressure coolant. Voprosy Atomnoi Nauki I Tekhniki. Ser. Yaderno-reaktornye Konstanty (4), 131–146 (2021). In Russian

  2. Davidenko, V.D., Zinchenko, A.S., Kharchenko, I.K.: Integral non-stationary neutron transfer equations for calculating the kinetics of nuclear reactors by the Monte Carlo method. Voprosy Atomnoi Nauki I Tekhniki. Ser. Fizika Yadernykh React. (1), 11–16 (2015). In Russian

  3. Gomin, E.A., Davidenko, V.D., Zinchenko, A.S., Kharchenko, I.K.: Calculation of the value function and the effective fraction of delayed neutrons by the Monte Carlo method. Voprosy Atomnoi Nauki I Tekhniki. Ser. Fizika Yadernykh React. (3), 22–30 (2016). In Russian

  4. Gomin, E.A., Davidenko, V.D., Zinchenko, A.S., Kharchenko, I.K.: Determining the lifetime of instantaneous fission neutrons by the Monte Carlo method. Voprosy Atomnoi Nauki I Tekhniki. Ser. Fizika Yadernykh React. (3), 16–21 (2016). In Russian

  5. Gomin, E.A., Davidenko, V.D., Zinchenko, A.S., Kharchenko, I.K.: Modeling the kinetics of a nuclear reactor by the Monte Carlo method. Voprosy Atomnoi Nauki I Tekhniki. Ser. Fizika Yadernykh React. (5), 4–16 (2016). In Russian

  6. Bell, D., Glesston, S.: Theory of nuclear reactors. Atomizdat, Мoscow (1974). In Russian

    Google Scholar 

  7. Zborovskii, V.G., Khoruzhii, O.V., Likhanskii, V.V.: Coherent simulation of thermal and neutronic parameters in the reactor core with a water coolant of a supercritical pressure. Voprosy Atomnoi Nauki I Tekhniki. Ser. Yaderno-reaktornye Konstanty (3), 100–114 (2023). In Russian

  8. Belousov, V.I., Davidenko, V.D., Dyachkov, I.I.: Linked neutronic-physical and thermal-hydraulic calculations of the test model of a reactor with supercritical pressure water using the Monte Carlo method. Voprosy Atomnoi Nauki I Tekhniki. Ser. Yaderno-reaktornye Konstanty (1), 24–40 (2023). In Russian

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Authors and Affiliations

  1. NRC “Kurchatov Institute”, Moscow, Russian Federation

    V. I. Belousov, V. D. Davidenko, I. I. Dyachkov, N. N. Elkin, M. R. Malkov, M. V. Ioannisian, M. G. Chernetskii, A. A. Chernitskaya, V. G. Zborovskii, V. V. Likhanskii & O. V. Khoruzhii

  2. Physical Institute RAS, Moscow, Russian Federation

    V. G. Zborovskii, V. V. Likhanskii & O. V. Khoruzhii

Authors
  1. V. I. Belousov
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  2. V. D. Davidenko
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  3. I. I. Dyachkov
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  4. N. N. Elkin
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  5. M. R. Malkov
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  6. M. V. Ioannisian
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  7. M. G. Chernetskii
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  8. A. A. Chernitskaya
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  9. V. G. Zborovskii
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  10. V. V. Likhanskii
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  11. O. V. Khoruzhii
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Corresponding author

Correspondence to A. A. Chernitskaya.

Additional information

Translated from Atomnaya Energiya, Vol. 134, No. 5–6, pp. 226–230, May–June, 2023.

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Original article submitted December 13, 2022.

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Belousov, V.I., Davidenko, V.D., Dyachkov, I.I. et al. KIR-TG code for interconnected thermo-hydraulic and neutron-physical test calculations of VVER-SKD reactors. At Energy (2024). https://doi.org/10.1007/s10512-024-01059-x

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  • DOI: https://doi.org/10.1007/s10512-024-01059-x

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