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Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage

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The approaches used in the EUCLID/V2 integrated code to calculate the core neutronics of a sodium-cooled fast reactor at the core destruction stage are described. Information is offered about the features of the operational algorithms of the SAFR severe accident module and the DN3D neutronics module. The ability of the integrated code to correctly calculate the processes involving core destruction is shown for an LOC accident.

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References

  1. N. A. Mosunova, “Integral code EUCLID/V1 for justifying the safety of fast neutron reactors with liquid-metal coolant. Part 1.Basic models,” Teploenergetika, No. 5, 69–84 (2018).

  2. A. A. Butov, V. S. Zhdanov, I. A. Klimonov, et al., “Physical models for calculating the destruction of a fuel rod and the core of a reactor with a liquid-metal coolant, implemented in the EUKLID/V2 code,” Teploenergetika, No. 5, 1–10 (2019).

  3. H. Yamano, Y. Tobita, and S. Fujita, “A three-dimensional neutronics-thermohydraulics simulation of core disruptive accident in sodium-cooled fast reactor,” Nucl. Eng. Design, 239, 1673–1681 (2009).

    Article  Google Scholar 

  4. X.-N. Chen, R. Li, F. Belloni, et al., “Safety studies for the MYRRHA critical core with the SIMMER-III code,” Ann. Nucl. Energy, 110, 1030–1042 (2017).

    Article  Google Scholar 

  5. J. Cahalan, F. Dunn, J. Herzog, et al., The SAS4A/SASSYS-1 Safety Analysis Code System, Chpt. 4, Reactor Point Kinetics, Decay Heat, and Reactivity Feedback, ANL/NE-12/4 (2012).

  6. G. Bell and S. Glasstone, Nuclear Reactor Theory [Russian translation], Atomizdat, Moscow (1974).

  7. Yu. Yu. Drobyshev and E. F. Seleznev, “Calculation of reactivity effects for the active zones of reactor installations on fast neutrons in the software and hardware complex GEFEST,” Vopr. At. Nauki Tekhn. Ser. Fiz. Yad. Reakt., No. 2, 44–52 (2017).

  8. Yu. M. Ashurko, A. V. Volkov, and K. F. Raskach, “Development of software modules for calculation of beyond design basis accidents in fast reactors, taking into account spatio-temporal kinetics,” At. Energiya, 114, No. 2, 63–67 (2013).

    Google Scholar 

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Correspondence to E. V. Usov.

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Translated from Atomnaya Énergiya, Vol. 132, No. 4, pp. 204–210, April, 2022.

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Koltashev, D.A., Mosunova, N.A., Strizhov, V.F. et al. Computational Aspects of Core Neutronics Calculation of Sodium-Cooled Fast Reactor at the Core Destruction Stage. At Energy 132, 212–218 (2022). https://doi.org/10.1007/s10512-023-00930-7

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  • DOI: https://doi.org/10.1007/s10512-023-00930-7

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