Skip to main content
Log in

Reasons for and against the oxygen dosage in condensate feed circuits of nuclear power plants with RBMK-1000 reactors

  • Articles
  • Published:
Soviet Atomic Energy Aims and scope

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.

Institutional subscriptions

Literature Cited

  1. I. A. Varovin, A. P. Eperin, M. P. Umanets, and V. G. Shcherbina, “Ten-year experience of operating the Leningrad NPP,” At. Énerg.,55, No. 6, 349 (1983).

    Google Scholar 

  2. M. E. Shitsman, Yu. I. Timofeev, L. S. Midler, et al., “27,000 h of the NRG operation without serivce acid washing,” Énergetik, No. 12, 4 (1978).

    Google Scholar 

  3. Yu. A. Egorov and I. Ya. Emel'yanov, “The state and problems of studying the radiation safety at the NPP in connection with further development of nuclear power,” in: Radiation Safety and Protection at the NPP [in Russian], Énergoizdat,7, Mosocw (1982), p. 5.

    Google Scholar 

  4. Yu. A. Egorov, A. A. Noskov, V. P. Sklyarov, et al., “The study and use of the TRAKT-1 model for calculation of the corrosion products activity in the technological circuit of the NPP with a channel-type reactor,” ibid., Atomizdat,5, Moscow (1981), p. 5.

    Google Scholar 

  5. V. S. Grechishkin, Yu. A. Egorov, G. N. Krasnozhen, et al., “Radiation Conditions at the Chernobyl'skaya NPP in the Initial Operation Period,” ibid., Énergoizdat,7, Moscow (1982), p. 92.

    Google Scholar 

  6. N. I. Bogdanov, A. V. Borunova, Yu. A. Egorov, et al., “Corrosion Products in the CCL (Controlled Circulation Loop) of the NPP with the RBMK Reactor,” ibid., Énergoizdat,8, Moscow (1984), p. 22.

    Google Scholar 

  7. E. P. Anan'ev, A. B. Andreeva, I. S. Dubrovskii, et al., “Efficiency of using the neutral-oxygen water chemistry regime in operating the NPP boiling shell-type reactor,” At. Énerg.,52, No. 1, 10–14 (1982).

    Google Scholar 

  8. N. I. Gruzdev, Z. V. Deeva, B. É. Shkol'nikova, et al., “Possibility of the development of brittle fractures in the heat boiler surface in the neutral-oxidizing regime,” Teploénergetika, No. 7, 8 (1983).

    Google Scholar 

  9. V. I. Gorin, “Some results of operating power units at supercritical pressure in neutral-oxidizing water regime” ibid. p. 2.

    Google Scholar 

  10. N. A. Lyashevich, “Operation reliability of heat surfaces of power units in the water regime with the oxidant dosage,” ibid., p. 11.

    Google Scholar 

  11. G. P. Sutotskii, G. V. Vasilenko, Yu. V. Zenkevich, et al., “Water chemistry regimes of SCP (supercritical pressure) units,” in: Water Treatment and Water Chemistry and Corrosion of the SPP and NPP [in Russian], TsKTI (Tsentr. NIiPKkotloturbinnyi Inst.),158, Leningrad (1978), p. 20.

    Google Scholar 

  12. A. I. Zabelin, A. B. Andreeva, Yu. V. Chechetkin, et al., “Corrosion and Activation in the Circuit of the NPP with a Boiling Reactor in Neutral Water Chemistry Regime without Correction,” Preprint 364 [in Russian], NIIAR-5, Dimitrovgrad (1979), pp. 1–14.

  13. A. I. Zabelin, A. B. Andreeva, V. M. Eshcherkin, et al., “Use of carbon steel in the water chemistry regime without correction of the NPP VK-50” At. Énerg.,49, No. 4, 229–232 (1980).

    Google Scholar 

  14. A. I. Zabelin, “Study of Water Chemistry Regimes of the NPP VK-50,” Preprint 538 [in Russian], NIIAR-23, Dimitrovgrad (1982).

  15. V. V. Gerasimov, Steel Corrosion in Neutral Water Media [in Russian], Metallurgiya, Moscow (1981).

    Google Scholar 

  16. V. V. Gerasimov, Corrosion of Reactor Materials [in Russian], Atomizdat, Moscow (1981).

    Google Scholar 

  17. J. Mushima, “Water chemistry in the Japanese light water reactors,” in: Proc. IAEA Specialists Meetings on Influence of Power Reactor Water Chemsitry on Fuel Cladding Reliability. Italy, Pisa, 12–16 Oct. 1981. Vienna: IAEA, 1982, p. 230.

    Google Scholar 

  18. J. Danko and K. Stahlkopf, “An overview of boiling water reactor pipe cracking,” J. Pressure Vessels and Piping, No. 9, 401–419 (1981).

    Google Scholar 

  19. C. Cheng, “Intergranular stress-assisted corrosion cracking of austenitic alloys in water-cooled nuclear reactors,” J. Nucl. Mater.,57, No. 11 (1975).

  20. W. Casto, “Recent occurrences at nuclear reactors and their causes,” Nucl. Safety,15, No. 4, 466–477 (1974).

    Google Scholar 

  21. W. Casto, “Recent occurrences at nuclear reactors and their causes,” ibid., No. 6 742–750

    Google Scholar 

  22. “Pipe cracking in boiling water reactors,” Nuclear Regulatory Commission report, Nucl. Safety,17, No. 4, 475 (1976).

  23. D. Locke, “Review of experience with water reactor fuels 1968–1973,” Nucl. Eng. Design,33 No. 2, 94 (1975).

    Google Scholar 

  24. M. Taylor, “Boiling water reactor stress corrosion cracking of piping-utility industry research program,” ibid.,69, No. 2, 223–227 (1982).

    Google Scholar 

  25. “Hydrogen stops growing cracks in BWRs,” Nucl. Eng. Int.,25, No. 295, 6 (1980).

  26. G. M. Kalinin, “Intercrystalline corrosion cracking and methods of recovering NPP pipelines,” At. Tekh. Rubezhom, No. 1, 17–20 (1985).

    Google Scholar 

  27. O. I. Martynova, “Further development of oxidizing water chemistry regime at power units with direct-flow channels in Western Europe,” Energokhozyaistvo Rubezhom, No. 3, 8–13, (1982).

    Google Scholar 

  28. “Structure materials corrosion under operation regimes of the first loop of the NPP with boiling reactors. Stainless, and pearlitic steels and zirconium alloys,” in: Proc. of the Jubilee Conf. on the Occasion of the 20th Anniversary of Nuclear Power Engineering [in Russian], Obninsk, June 25–27 (1974), p. 201.

  29. A. S. Zaimovskii, A. V. Nikulina, and N. G. Reshetnikov, Zirconium Alloys in Nuclear Power Engineering [in Russian], Énergoizdat, Moscow (1981).

    Google Scholar 

Download references

Authors

Additional information

Translated from Atomnaya Énergiya, Vol. 59, No. 6, pp. 409–413, December, 1985.

Rights and permissions

Reprints and permissions

About this article

Cite this article

Gerasimov, V.V., Gromova, A.I., Baranov, V.N. et al. Reasons for and against the oxygen dosage in condensate feed circuits of nuclear power plants with RBMK-1000 reactors. At Energy 59, 976–982 (1985). https://doi.org/10.1007/BF01132603

Download citation

  • Received:

  • Issue Date:

  • DOI: https://doi.org/10.1007/BF01132603

Keywords

Navigation