Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Problems of Increasing the Reliability of BN-600 Steam Generators

9/10/2025 2025 - #03 Nuclear power plants

Bel’tyukov A.I. Govorov P.P. Nosov Yu.V. Shcheklein S.E. Tashlykov O.L.

DOI: https://doi.org/10.26583/npe.2025.3.05

UDC: 621.039

Presented are the features of steam generators heated by sodium coolant. The design of the steam generator PGN-200M and its main characteristics are described.

Information on intercircuit leaks in the steam generator modules and a list of research works carried out to determine the causes of these leaks are given. The solutions aimed at increasing the reliability of the steam generator are described. The main works performed within the framework of the program for metal research to substantiate the decision to extend the service life of evaporators are described. The programs for performing works on changing the PGN-200M operational transient modes are presented that ensure the extension of the service life. The article also presents the results of tests to determine the maximum value of the deposit layer at which an intensive process of metal corrosion begins.

The results of experimental studies and tests carried out on the equipment of steam generator units of fast sodium-cooled reactor power plants of the Beloyarsk NPP are analyzed and systematized. The results of the calculation and experimental substantiation of the operating modes of once-through steam generators are presented to ensure the safety of power units with fast reactors and to increase the stability of the power unit operation in case of individual equipment failures. All the results of the experimental studies were implemented in the regulations and operating instructions for NPPs with BN-600 and BN-800.

References

  1. Tashlykov O., Shcheklein S., Nosov Y., Smyshlaeva O. Ecological foresight in the nuclear power of XXI century. International journal of energy production and management. 2016;1(2):133–140. URL: https://iieta.org/journals/ijepm/paper/10.2495/EQ-V1-N2-133–140 (accessed Jul. 18, 2025).
  2. Tashlykov O.L., Sesekin A.N., Klimova V.A., Mahmoud K.A. Optimization of the route of the refueling machine to reduce the refueling time: Case study of the BN-800 reactor. Nuclear Engineering and Design. 2025;431:113725, 9 p. DOI: https://doi.org/10.1016/j.nucengdes.2024.113725
  3. Rassokhin N.G. Steam generator installations of nuclear power plants. Moscow, Energoatomizdat Publ., 1987, 384 p. (in Russian).
  4. Troyanov M.F. Development of the scientific-technological bases of fast power reactors. Atomic energy. 1981;50(2):87–95. DOI: https://doi.org/10.1007/BF01121162
  5. Poplavskiy V.M., AshurkoYu.M., Baklushin R.P., Kamaev A.A., Denisov V.V., Trunov N.B., Oshkanov N.N., Bakanov M.V., Potapov O.A., ShtyndaYu.E., Korolkov A.S. Review of steam generators used in Russian sodium-cooled fast reactors and their operating experience. 2nd IAEA Coordination Research Meeting for the Coordinated Research Project on ‘Analysis of Operating Experience of Fast Reactor Equipment and Systems and Lessons Learned from This Experience’, Vienna, Austria, 20–23 May 2008 (in Russian).
  6. Tashlykov O.L. Bel’tyukov A.I. Steam generators of nuclear power plants: textbook. Yekaterinburg, Ural Federal University Publ., 2019, 304 p. ISBN 978-5-7996-2675-4 (in Russian).
  7. Tashlykov O.L. Steam Generating Plant Repair Technologies: A Tutorial. Yekaterinburg. USTU-UPI Publ., 2009, 118 p. (in Russian).
  8. Beltyukov A.I., Karpenko A.I., Poluyaktov S.A., Tashlykov O.L., Titov G.P., Tuchkov A.M., Shcheklein S.E. Nuclear Power Plants with Fast Neutron Reactors with Sodium Coolant: A Textbook. In 2 parts. Part 1. Yekaterinburg, UrFU Publ., 2013, 548 p. ISBN 978-5-321-02324-2 (in Russian).
  9. Denisov V.V., Likhosherst A.N., MaksimenkoYu.V., Titov V.F. Calculation and experimental substantiation of the possibility of extending the service life of PGN-200M evaporator . Bezopasnost’ ekspluatatsii Beloyarskoy AES. Collection of scientific papers. Yekaterinburg. URO RAN Publ., 1994. 223 p. ISBN 5-7691-0469-4 (in Russian).
  10. Beltyukov A.I., Karpenko A.I., Poluyaktov S.A., Tashlykov O.L., Titov G.P., Tuchkov A.M., Shcheklein S.E. Nuclear Power Plants with Fast Neutron Reactors with Sodium Coolant: A Textbook. In 2 parts. Part 2. Yekaterinburg, UrFU Publ., 2013, 420 p. ISBN 978-5-321-02323-4 (in Russian).
  11. Research of heat exchange tube from evaporator 5IB2 of BN-600 unit after resource operation of about 68000 hours: Report No. 127-0-115. Podolsk, OKB ‘Gidropress’ Publ., 1991.
  12. Sheinkman A.G., Bel’tyukov A.I., Govorov P.P. Hydrodynamic instability in the evaporators of BN-600 steam generator. High Temperature. 1998;36(3):496–505. URL: https://www.mathnet.ru/links/caa527f442c1fd425123b6846ea201a2/tvt2433.pdf (accessed Jul. 18, 2025) (in Russian).
  13. Delahaye J., Ghio M., Riethmüller M. Heat transfer and hydrodynamics of two-phase flows in nuclear power engineering. Moscow, Energoatomizdat Publ., 1984, 424 p.

fast sodium reactor sodium coolant steam generator sectional modular steam generator evaporation module superheater module intercircuit leak service life extension deposits (impurities) on the surface of heat exchange tubes corrosion pitting

Link for citing the article: Bel’tyukov A.I., Govorov P.P., Nosov Yu.V., Shcheklein S.E., Tashlykov O.L. Problems of Increasing the Reliability of BN-600 Steam Generators. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 3, pp. 74-90; DOI: https://doi.org/10.26583/npe.2025.3.05 (in Russian).

Open PDF file