Skip to main content
SpringerLink
Log in

The Concept of a Nuclear Power Unit on the Basis of a Low-Power Multipurpose Test Research Reactor with Supercritical Light-Water Coolant

  • NUCLEAR POWER PLANTS
  • Published:
Thermal Engineering Aims and scope Submit manuscript

Abstract

Herein is presented a preliminary concept of a nuclear power installation (NPI) based on a low-power multipurpose test research reactor with a supercritical pressure light water coolant (LMTRR-SCP), which can operate as a test or research reactor, and has the following capabilities: substantiation of operating conditions for a supercritical water-cooled power reactor in the fast neutron spectrum; adjustment of the design operating regimes of the reactor with supercritical coolant conditions (including reactor startup, attainment of the energy power level, switch-over between power levels, rated power operation, shutdown, etc.); reactor irradiation of promising types of nuclear fuel, absorbing and structural materials for nuclear installations with fast, intermediate, or thermal neutron spectrum; comprehensive experimental and numerical investigations to obtain information required for development and verification of numerical codes; evaluation of new types of equipment for various process systems (including elements of emergency cooling systems, steam generators, etc.), instruments, and control, monitoring, and diagnostics systems for power reactors of various types. Investigations into the closed nuclear fuel cycle (CNFC) problem; utilization of actinides and handling of long-lived fission products, including pilot demonstration closure of the fuel cycle; mastering of processes for the manufacture of radionuclide products for various applications; production of modified materials; and use of the reactor’s thermal energy for heat and power generation. A potential also exists for the development of international cooperation within the scope of joint research programs on the basis of LMTRR-SCP.

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

Access this article

Log in via an institution

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

Instant access to the full article PDF.

Institutional subscriptions

Fig. 1.
Fig. 2.
Fig. 3.
Fig. 4.
Fig. 5.
Fig. 6.
Fig. 7.
Fig. 8.
Fig. 9.

Similar content being viewed by others

REFERENCES

  1. A. A. Sedov, S. B. Pustovalov, T. D. Shchepetina, and S. S. Simonov, “NPP with SCW nuclear power installation,” in Proc. 10th Int. Symp. on Supercritical Water-Cooled Reactors (ISSCWR-10), Prague, Czech Republic, Mar. 15–18, 2021, p. 001.

  2. A. S. Lapin, A. S. Bobryashov, V. Yu. Blandinskii, and E. A. Bobrov, “Analysis of system characteristics of a reactor with supercritical coolant parameters,” Izv. Vyssh. Uchebn. Zaved., Yad. Energ., No. 3, 93–101 (2020). https://doi.org/10.26583/npe.2020.3

  3. A. S. Lapin, A. S. Bobryashov, V. Yu. Blandinskii, and E. A. Bobrov, “Assessment of the system characteristics of a reactor with supercritical coolant parameters for various fuel cycles,” Vopr. At. Nauki Tekh., Ser.: Yad.-Reakt. Konst., No. 3, 51–62 (2020). https://doi.org/10.55176/2414-1038-2020-3-51-62

  4. A. S. Lapin, V. Yu. Blandinskii, E. A. Bobrov, and V. Yu. Kukanov, “Investigation of ways to reduce the void effect of reactivity in a reactor with supercritical coolant parameters,” in Future of Nuclear Energy (AtomFuture 2020): Proc. 16th Int. Sci. and Pract. Conf., Obninsk, Russia, Nov. 23–24, 2020, pp. 22–23.

  5. A. S. Lapin, A. S. Bobryashov, V. Yu. Blandinskii, and E. A. Bobrov, “Use of a reactor with supercritical coolant parameters in a nuclear power system with various fuel cycles,” in Scientific Research and Technological Developments to Ensure the Development of Next-Generation Nuclear Technologies: Proc. 10th All-Russian Youth’s Conf., Dimitrovgrad, Russia, Mar. 17–18, 2021, pp. 5–6.

  6. Ya. A. Kotov, V. V. Kolesov, V. A. Nevinitsa, and P. A. Fomichenko, “Study of reactivity effects and other neutronic and physical characteristics of VVER-SKD,” in Neutronica-2022: Proc. Conf., Obninsk, 2022.

  7. V. E. Kashirina and Ya. A. Kotov, “Investigation of the components of the density effect of reactivity in the VVER-SKD reactor,” in Volga-2022: Proc. Conf., Tver, Russia, Sept. 5–9, 2022.

  8. A. P. Glebov and A. V. Klushin, “Investigations on justification and development of concept of directsteam NPP with water cooled reactor at supercritical parameters with fast resonance spectrum,” Izv. Vyssh. Uchebn. Zaved., Yad. Energ., No. 4, 118–127 (2013). https://doi.org/10.26583/npe.2013.4.15

  9. A. P. Glebov, Yu. D. Baranaev, I. V. Moskovchenko, and P. L. Kirillov, “SCWR development from concept to test reactor,” Vopr. At. Nauki Tekh., Ser.: Yad.-Reakt. Konst., No. 3, 30–44 (2019). https://doi.org/10.55176/2414-1038-2019-3-30-44

  10. V. A. Mokhov, V. Ya. Berkovich, M. P. Nikitenko, A. N. Churkin, V. M. Makhin, P. L. Kirillov, Yu. D. Baranaev, and A. P. Glebov, “Conceptual proposals on the test reactor of VVER-SCP,” in Proc. 7th Int. Symp. on Supercritical Water-Cooled Reactors (ISSCWR-7), Helsinki, Finland, Mar. 15–18, 2015, p. 2053.

  11. A. A. Sedov, P. S. Polyakov, S. B. Pustovalov, V. V. Parshin, and S. S. Simonov, “Main results of test tests of a closed loop with natural circulation of a light water coolant at supercritical pressure,” Therm. Eng. 70, 223–235 (2023). https://doi.org/10.56304/S0040363623030074

    Article  Google Scholar 

  12. K. B. Kosourov, Yu. M. Semchenkov, and Ya. I. Shtrombakh, Practical Fundamentals of Development and Justification of the Technical Characteristics and Safety of Operation of VVER-Type Reactor Plants: Textbook (Kurchatovskii Inst., Moscow, 2015) [in Russian].

    Google Scholar 

  13. X-5 Monte Carlo Team, MCNP–A General Monte Carlo N-Particle Transport Code, Version 5, Vol. I: Overview and Theory, Los Alamos National Laboratory Report LAUR-03-1987 (2008).

  14. V. Yu. Blandinskii, V. V. Kolesov, V. A. Nevinitsa, P. A. Fomichenko, A. A. Sedov, A. A. Frolov, S. B. Pustovalov, M. V. Shchurovskaya, S. S. Simonov, Yu. E. Pesnya, V. V. Trofimchuk, V. A. Nasonov, and I. Yu. Zhemkov, “Peculiarities of changes in the isotopic composition of pilot fuel elements of a VVER-SKD reactor under successive irradiation in the fast and thermal neutron spectrum,” Vopr. At. Nauki Tekh., Ser.: Fiz. Yad. Reakt., No. 2, 90–96 (2022).

  15. F. W. Dittus and L. M. K. Boelter, “Heat transfer in automobile radiators of the tubular type,” Int. Commun. Heat Mass Transfer 12, 3–22 (1985). https://doi.org/10.1016/0735-1933(85)90003-X

    Article  MATH  Google Scholar 

  16. D. D. Lanning, C. E. Beyer, and K. G. Geelhood, FRAPCON-3 Updates, Including Mixed-Oxide Fuel Properties, NUREG/CR-6534, PNNL-11513 (Pacific Northwest National Laboratory, Richland, WA, 2005), Vol. 4.

  17. L. J. Siefken, E. W. Coryell, E. A. Harvego, and J. K. Hohorst, SCDAP/RELAP5/MOD 3.3 code manual: MATPRO. A Library of Materials Properties for Light-Water-Reactor Accident Analysis, Technical Report NUREG/CR-6150 (Nuclear Regulatory Commission, U.S., 2001), Vol. 4, Rev. 2.

  18. Status and Advances in MOX Fuel Technology (International Atomic Energy Agency, Vienna, Austria, 2003), in Ser.: Technical Reports Series, Vol. 415.

  19. G. G. Gadzhiev, Z. M. Omarov, Kh. Kh. Abdullaev, A. G. Bakmaev, and M. M. Magomedov, “Thermal and electrical properties of ChS-68 steels,” in Ordering in Minerals and Alloys (OMA-19): Proc. 19th Int. Symp., Rostov-on-Don, Russia, Sept. 10–15, 2016, pp. 49–52.

  20. A. N. Filonin, E. N. Shcherbakov, A. N. Ogorodov, and O. S. Korostin, “Relationship between the initial values of the elasticity characteristics of austenitic clad steels of fuel rods in BN reactors with their subsequent swelling,” in Proc. 5th Industry Seminar on Strength and Reliability of Core Elements of Power Nuclear Reactors, Obninsk, 1991, p. 39.

  21. V. P. Tarasikov, G. A. Birzhevoi, and S. V. Shulepin, Influence of Neutron Irradiation on Physical and Mechanical Properties of Steels and Alloys of Domestic Nuclear Reactors (Fizmatlit, Moscow, 2020) [in Russian].

    Google Scholar 

  22. V. V. Chuev, V. N. Lanskikh, and A. N. Ogorodov, “Operability of fuel assemblies of fast reactors,” in Studies of Structural Materials of Core Elements of Fast Sodium Reactors (Ural. Otd. Ross. Akad. Nauk, Yekaterinburg, 1994) [in Russian].

    Google Scholar 

  23. A. N. Ogorodov, S. E. Astashov, E. A. Kozmanov, V. V. Chuev, A. G. Sheikman, O. S. Korostin, and L. M. Zabud’ko, “Shaping of fuel claddings made of ChS-68 steel at doses of 60–93 dpa in the BN-600 reactor,” in Proc. 4th Interindustry Conf. on Reactor Materials Science, Dimitrovgrad, 1996, pp. 110–121.

  24. Yu. A. Zakharko, A. S. Stepanov, and A. A. Sedov, “Analytical solutions of thermoviscoelastic equations for cylindrical bodies as applied to predicting the behavior of fuel elements in power reactors,” Vopr. At. Nauki Tekh., Ser.: Fizika Yad. Reakt., No. 1, 55–63 (2021).

  25. V. M. Zorin, A. S. Shamarokov, and S. B. Pustovalov, “The new generation of high-pressure heaters for steam turbine units at nuclear power plants,” Therm. Eng. 68, 285–294 (2021). https://doi.org/10.1134/S004060152104008X

    Article  Google Scholar 

  26. A. S. Shamarokov, V. M. Zorin, S. B. Pustovalov, and E. A. Mikhushkina, “The new generation of moisture separators-reheaters for steam-turbine units of nuclear power plants (NPP) with VVER-reactors,” Therm. Eng. 69, 691–701 (2022). https://doi.org/10.1134/S0040601522080080

    Article  Google Scholar 

Download references

Funding

The work was funded by AO Concern Rosenergoatom.

Author information

Authors and Affiliations

  1. National Research Center (NRC) Kurchatov Institute, 123184, Moscow, Russia

    A. A. Sedov, V. Yu. Blandinskii, Ya. A. Kotov, D. S. Kuzenkova, A. S. Lapin, V. A. Nevinitsa, S. B. Pustovalov, A. S. Stepanov, S. A. Subbotin, P. A. Fomichenko, B. I. Fonarev & A. A. Frolov

Authors
  1. A. A. Sedov
    View author publications

    You can also search for this author in PubMed Google Scholar

  2. V. Yu. Blandinskii
    View author publications

    You can also search for this author in PubMed Google Scholar

  3. Ya. A. Kotov
    View author publications

    You can also search for this author in PubMed Google Scholar

  4. D. S. Kuzenkova
    View author publications

    You can also search for this author in PubMed Google Scholar

  5. A. S. Lapin
    View author publications

    You can also search for this author in PubMed Google Scholar

  6. V. A. Nevinitsa
    View author publications

    You can also search for this author in PubMed Google Scholar

  7. S. B. Pustovalov
    View author publications

    You can also search for this author in PubMed Google Scholar

  8. A. S. Stepanov
    View author publications

    You can also search for this author in PubMed Google Scholar

  9. S. A. Subbotin
    View author publications

    You can also search for this author in PubMed Google Scholar

  10. P. A. Fomichenko
    View author publications

    You can also search for this author in PubMed Google Scholar

  11. B. I. Fonarev
    View author publications

    You can also search for this author in PubMed Google Scholar

  12. A. A. Frolov
    View author publications

    You can also search for this author in PubMed Google Scholar

Corresponding author

Correspondence to S. B. Pustovalov.

Additional information

Translated by T. Krasnoshchekova

Rights and permissions

Reprints and permissions

About this article

Check for updates. Verify currency and authenticity via CrossMark

Cite this article

Sedov, A.A., Blandinskii, V.Y., Kotov, Y.A. et al. The Concept of a Nuclear Power Unit on the Basis of a Low-Power Multipurpose Test Research Reactor with Supercritical Light-Water Coolant. Therm. Eng. 70, 323–338 (2023). https://doi.org/10.1134/S0040601523050063

Download citation

  • Received:

  • Revised:

  • Accepted:

  • Published:

  • Issue Date:

  • DOI: https://doi.org/10.1134/S0040601523050063

Keywords:

Search

Navigation