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The influence of the high-temperature coolant purification system at nuclear power stations equipped with VVER-1000 reactors on the formation of dose burdens

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Abstract

It is shown that the effectiveness of using high-temperature filters for purifying the coolant at nuclear power stations equipped with VVER-1000 reactors is mainly determined by the precipitation constant of activated corrosion products dispersed in the coolant.

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References

  1. L. M. Luzanova, N. V. Zadonskii, A. F. Shvoev, et al., “Activated Corrosion Products in the Reactor Coolant Circuit of a VVER-1000 Reactor,” At. Energ. 68(1), 52–54 (1990).

    Article  Google Scholar 

  2. V. G. Kritskii, V. V. Tsarev, N. A. Prokhorov, et al., “Analyzing the Performance of the High-Temperature Mechanical Filter at Operating Nuclear Power Stations with VVER-1000 Reactors,” Teploenergetika, No. 7, 15–19 (1992) [Therm. Eng., No. 7 (1992)].

  3. A. A. Efimov, L. N. Moskvin, B. A. Gusev, et al., “The Influence of High-Temperature Filtration on the Composition of Impurities in the Reactor Coolant of Power Units Built around VVER-1000 Reactors,” Teploenergetika, No. 10, 49–52 (1992) [Therm. Eng., No. 10 (1992)].

  4. A. I. Kasperovich, B. I. Kolesov, and N. G. Sandler, “Water-Chemistry Processes in the Reactor Installations of Nuclear-Powered Ice Breakers and Floating Power Units,” At. Energ. 81(4), 261–266 (1996).

    Google Scholar 

  5. A. P. Veselkin and A. V. Nikitin, “Activation of Corrosion Products in Nuclear Reactors,” At. Energ. 21(3), 184–189 (1966).

    Article  Google Scholar 

  6. A. S. Tevlin, “Development of a Model for Simulating the Accumulation of Radioactive Corrosion Products in the Equipment of Nuclear Power Stations with Boiling-Water Reactors,” At. Energ. 58(4), 242–246 (1985).

    Article  MathSciNet  Google Scholar 

  7. M. I. Ryabov and N. I. Gruzdev, “Analyzing the Mass Transfer of Corrosion Products in the Loop of a Nuclear Power Station Equipped with a Boiling-Water Reactor,” At. Energ. 60(6), 379–382 (1986).

    Article  Google Scholar 

  8. M. I. Ryabov, “Calculation of Radionuclide Precipitation Constants in Nuclear Reactors on the Basis of Model Concepts about Sedimentation of Iron Corrosion Products,” in Radiation Safety and Protection of Nuclear Power Stations (Energoatomizdat, Moscow, 1991), issue 13, pp. 128–132.

    Google Scholar 

  9. Yu. A. Egorov and A. A. Noskov, “A New Model for Transfer and Accumulation of Main Corrosion Products in the Process Circuits of Nuclear Power Stations,” in Radiation Safety and Protection of Nuclear Power Stations (Energoatomizdat, Moscow, 1984), issue 8, pp. 6–22.

    Google Scholar 

  10. Yu. A. Egorov, A. A. Noskov, V. P. Sklyarov, and V. Ya. Tolstykh, “On Calculating the Activity of Corrosion Products in the Process Circuits of Nuclear Power Stations,” in Radiation Safety and Protection of Nuclear Power Stations (Energoatomizdat, Moscow, 1977), issue 3, pp. 17–27.

    Google Scholar 

  11. T. M. Ziganshin, I. G. Kobzar’, Yu. V. Chechetkin, et al., “Studying the Accumulation of Corrosion Products in the Primary Coolant Circuit of an NPS Equipped with a Boiling-Water Reactor Based on the Experience Gained at the VK-50 Nuclear Power Station,” in Radiation Safety and Protection of Nuclear Power Stations (Energoatomizdat, Moscow, 1981), issue 5, pp. 22–27.

    Google Scholar 

  12. V. P. Sklyarov, “A Study of the Mass Transfer Constants for a Nuclear Power Station Equipped with a Pressure-Tube Reactor,” in Radiation Safety and Protection of Nuclear Power Stations (Energoatomizdat, Moscow, 1981), issue 5, pp. 27–35.

    Google Scholar 

  13. Yu. A. Egorov and A. A. Noskov, “The Coefficients for Mass Transfer of Corrosion Products in the Process Circuit of a Nuclear Power Station,” in Radiation Safety and Protection of Nuclear Power Stations (Energoatomizdat, Moscow, 1984), issue 8, pp. 67–71.

    Google Scholar 

  14. Yu. A. Egorov, A. A. Noskov, V. P. Sklyarov, et al., “A Study and Application of the TRAKT-1 Model for Calculating the Activity of Corrosion Products in the Process Circuit of a Nuclear Power Station Equipped with a Pressure-Tube Reactor,” in Radiation Safety and Protection of Nuclear Power Stations (Energoatomizdat, Moscow, 1981), issue 5, pp. 10–22.

    Google Scholar 

  15. V. M. Krasnoperov, “The Model of Deposition of Corrosion Products on the Nonheated Surfaces of Pipelines,” Teploenergetika, No. 5, 36–38 (2008) [Therm. Eng., No. 5 (2008)].

  16. I. S. Orlenkov, V. M. Krasnoperov, B. A. Gusev, and L. N. Moskvin, “Raising the Efficiency of Evacuating the Corrosion Products from the Primary Coolant Circuits of Water-Moderated Reactors (VVR) by Standard Decontaminating Filters,” Teploenergetika, No. 11, 17–19 (1998) [Therm. Eng., No. 11 (1998)].

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Original Russian Text © B.A. Gusev, V.M. Krasnoperov, 2011, published in Teploenergetika.

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Gusev, B.A., Krasnoperov, V.M. The influence of the high-temperature coolant purification system at nuclear power stations equipped with VVER-1000 reactors on the formation of dose burdens. Therm. Eng. 58, 396–398 (2011). https://doi.org/10.1134/S0040601511050089

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