Skip to main content
Log in

Three-Liquid, Two-Phase, Per-Channel Thermohydraulics Code Subchannel-Na/V1.0 for Single-Phase Sodium-Coolant Flows and Heat-Transfer: Key Models

  • Published:
Atomic Energy Aims and scope

The models used in the program SubChannel Na/V1 0 to calculate single-phase regimes of flow and heat-transfer for performing channel-by-channel (cellular) thermohydraulic calculations of sodium-cooled fuel assemblies (FA) are described. Modeling made it possible to obtain the distribution of the coolant temperature and velocity in the FA channels along the longitudinal and transverse sections of FA and the temperature of the fuel-rod cladding. The results of the validation of the program on the data of an experiment performed at ORNL (USA) on the 19-rod assembly FFM 2A are presented.

This is a preview of subscription content, log in via an institution to check access.

Access this article

Price excludes VAT (USA)
Tax calculation will be finalised during checkout.

Instant access to the full article PDF.

Similar content being viewed by others

References

  1. E. O. Adamov, White Paper on Nuclear Energy. Closed NFC with Fast Reactors, NIKIET, Moscow (2020).

  2. E. O. Adamov, R. M. Aleksakhin, L. A. Bolshov, et al., “Project Proryv – technological foundation for large-scale nuclear power engineering,” Izv. Akad. Nauk. Energetika, No. 1, 5–12 (2015).

  3. V. I. Rachkov, Yu. S. Khomyakov, and Yu. E. Shvetsov, “Russian codes for safety analysis of sodium-cooled fast reactors,”At. Energiya, 116, No. 4, 216–222 (2014).

    Google Scholar 

  4. P. L. Kirillov, V. P. Bobkov, A. V. Zhukov, et al., Handbook of Thermohydraulic Calculations in Nuclear Power Engineering, IzdAt, Moscow (2010), Vol. 1.

  5. M. Glück, An Overview about Modeling Approaches for Turbulent Mixing and Void Drift in Sub-Channel Analysis, Nova Sci. Publ., Erlangen (2009).

    Google Scholar 

  6. J. Fink and L. Leibowitz, Thermodynamic and Transport Properties of Sodium Liquid and Vapor, ANL (1995).

  7. J. Cox, D. Wagman, and V. Medvedev, CODATA Key Values for Thermodynamics, Hemisphere Publ. Corp., New York (1989).

    Google Scholar 

  8. 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).

    Google Scholar 

  9. V. M. Alipchenkov, A. V. Boldyrev, and D. P. Veprev, “Integral code EUCLID/V1 for justifying the safety of fast neutron reactors with a liquid metal coolant. Part 2: verification,” Teploenergetika, No. 9, pp. 57–72 (2018).

    Google Scholar 

  10. M. Fontana, R. MacPherson, P. Gnadt, et al., “Temperature distribution in the duct wall and at the exit of a 19-rod simulated LMFBR fuel assembly (FFM bundle 2A),” Nucl. Techn., 24, 176–200 (1974).

    Article  ADS  Google Scholar 

  11. M. Fontana, R. MacPherson, P. Gnadt, et al., Temperature Distribution in a 19-Rod Simulated LMFBR Fuel Assembly in a Hexagonal Duct (Fuel Failure Mockup Bundle 2A). Record of Experimental Data, ORNL (1973).

  12. E. V. Moiseenko and N. A. Mosunova, “Methodology for evaluating the uncertainties in computational results for substantiation of the safety of nuclear power plants,” Vopr. Rad. Bezopasn., No. 2, 24–34 (2018).

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to N. A. Mosunova.

Additional information

Translated from Atomnaya Énergiya, Vol. 132, No. 6, pp. 331–336, June, 2022.

Rights and permissions

Springer Nature or its licensor (e.g. a society or other partner) holds exclusive rights to this article under a publishing agreement with the author(s) or other rightsholder(s); author self-archiving of the accepted manuscript version of this article is solely governed by the terms of such publishing agreement and applicable law.

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Alipchenkov, V.M., Grudtsyn, Y.V., Mosunova, N.A. et al. Three-Liquid, Two-Phase, Per-Channel Thermohydraulics Code Subchannel-Na/V1.0 for Single-Phase Sodium-Coolant Flows and Heat-Transfer: Key Models. At Energy 132, 347–352 (2022). https://doi.org/10.1007/s10512-023-00958-9

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-023-00958-9

Navigation