Skip to main content
Log in

Certain Problems of Lengthened Cooldown of NPP–VVER Power Units in Accidents with Loss of Primary-Loop Coolant

  • Published:
Atomic Energy Aims and scope

The influence of certain physical phenomena on the reliability of cooldown of next-generation VVER cores during long-time passive cooldown in accidents with loss of coolant from the primary loop is analyzed. Heat removal from the residual energy release is shown to be impaired in accidents with a large primary-coolant leak associated with the accumulation of boric acid in the VVER-TOI flow path during prolonged flow from the second stage (GE-2) and third stage (GE-3) hydroaccumulators into the primary coolant loop. It is pointed out that high boric acid concentrations must be taken into account in the computational codes.

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. A. N. Gudoshnikov and Yu. A. Migrov, “Numerical simulation of VVER-640 residual heat removal to ultimate heat sink, taking into account the joint operation of passive safety systems,” Abstr. 7th Int. Sci. Techn. Conf. Ensuring the Safety of Nuclear Power Plants with VVER, Podol’sk, May 17–20, 2011, p. 34.

  2. Yu. A. Migrov and A. N. Gudoshnikov, “Analysis of Passive Cooling Processes of NPP Power Units with VVER-640 in Accidents with Loss of Coolant,” Tekhnol. Obesp. Zhizn. Tsik. Yad. Energ. Ustan., No. 4(6), 8–22 (2016).

  3. A. N. Gudoshnikov and Yu. A. Migrov, “Computational analysis of the operation of passive systems in accidents with leaks in the primary loop of NPP–VVER,” Abstr. 7th Int. Sci. Techn. Conf. Ensuring the Safety of Nuclear Power Plants with VVER, Podol’sk, May 17–20, 2011, p. 34.

  4. S. B. Alekseev, Experimental Studies of Hydrodynamic Crisis of Countercurrent Flows of Water and Steam in the Elements of NPP Equipment: Candidate Dissertation in Technical Sciences, St. Petersburg (2011).

  5. Yu. V. Yudov. “Accounting for the influence of non-condensable gases on interfacial heat and mass transfer in a two-fluid model of the KORSAR code,” Teploenergetika, No. 3, 42–50 (2018).

  6. A. V. Morozov, A. P. Sorokin, and A. V. Pityk, “Experimental determination of the thermophysical properties of boric acid for emergency regimes of VVER,” At. Energ., 125, No. 3, 159–164 (2018).

    Google Scholar 

  7. Summary of Tests to Determine the Physical Properties of Buffered and Unbuffered Boric Acid Solutions, Rep. WCAP-17021-NP, Westinghouse Electric Company (2010).

  8. Small Scale Unbuffered and Buffered Boric Acid Nucleate Boiling Heat Transfer Tests with Sump Debris in a Vertical 3×3 Rod Bundle, Rep. WCAP-17360-NP, Westinghouse Electric Company (2012).

Download references

Author information

Authors and Affiliations

Authors

Corresponding author

Correspondence to Yu. A. Migrov.

Additional information

Translated from Atomnaya Énergiya, Vol. 132, No. 2, pp. 105–109, February, 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

Migrov, Y.A., Gudoshnikov, A.N. Certain Problems of Lengthened Cooldown of NPP–VVER Power Units in Accidents with Loss of Primary-Loop Coolant. At Energy 132, 110–115 (2022). https://doi.org/10.1007/s10512-023-00912-9

Download citation

  • Received:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1007/s10512-023-00912-9

Navigation