Izvestiya vuzov. Yadernaya Energetika

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

On the Possibility of Cooling the High-Power VVER Reactor Pressure Vessel Using an Air-Droplet Spray in the Event of a Beyond Design Basis Accident

3/25/2025 2025 - #01 Global safety, reliability and diagnostics of nuclear power installations

Zaryugin D.G. Leskin S.T. Mikhin S.A. Sergeev V.V. Slobodchuk V.I.

DOI: https://doi.org/10.26583/npe.2025.1.06

UDC: 621.039.5

For reactors with high decay power (VVER-1000, VVER-1200, VVER-TOI, etc.), no reliable reactor vessel cooling is achieved via the concept of retaining the corium inside the reactor pressure vessel only by means of heat transfer with water in the process of its boiling within the outer barrel since high heat fluxes (density above 106 W/m2) cause a boiling evolving into film boiling and to a heat transfer crisis. A comparative analysis of different cooling systems shows that the most reliable and effective way to prevent the heat transfer crisis is an intensification of heat transfer on the cooled surface by using an air-droplet spray device (ADSD), which can be used to retain the core melt inside the reactor pressure vessel. The paper provides an overview of studies on gas-droplet cooling of high-temperature surfaces, and presents preliminary calculations using correlations of the non-wetting cooling mode as being of greatest interest for ADSD. Methods have been considered for simulating gas-droplet cooling in system codes. The qualitative agreement of the calculation results with experimental data is shown. The peculiarities of spray cooling of the large VVER reactor vessel are identified. A diagram of the possible locations of spray nozzles within the reactor barrel is demonstrated. Due to the lack of a single verified spray cooling model for high-temperature surfaces, experimental studies are considered to be the key approach in the scientific problem under consideration, that is cooling of the large VVER reactor vessel in the event of a beyond design basis accident.

References

  1. Rezepov V.K., Denisov V.P., Kirilyuk N.A., Dragunov Yu.G., Ryzhov S.B. WWER-1000 Reactors for Nuclear Power Plants. Moscow, Akademkniga Publ., 2003, 333 p. (in Russian).
  2. Sulatskii A.A., Chernyi O.D., Efimov V.K., Granovskii V.S. Burnout on the External Surface of a VVER Reactor Vessel. Thermal Engineering. 1998;45(11):913–918.
  3. Vertkov A.V., Komov A.T., Lyublinski I.E., Mirnov S.V., Varava A.N., Dedov A.V., Zaharenkov A.V, Frick P.G. The Use of Dispersed Gas-Liquid Flow for Cooling of the Tokamak T-10 Liquid Metal Limiter. Problems of Atomic Science and Technology. Ser. Thermonuclear Fusion. 2018;41(1):57–64. DOI: https://doi.org/10.21517/0202-3822-2018-41-1-57-64 (in Russian).
  4. Shteling V.S., Dedov A.V., Zakharenkov A.V., Komov A.T. , Shcherbakov P.P. An Experimental Study of Wall Thermal Stabilization Efficiency by a Spray Cooling. Thermal Engineering. 2022;69: 954–962. DOI: https://doi.org/10.1134/S0040601522120072
  5. Voitkov I.S., Volkov R.S., Kuznetsov G.V., Strizhak P.A. High-temperature Evaporation of Water Droplets in a Gaseous Medium. Technical Physics. 2017;62(12):1908–1911. DOI: https://doi.org/10.1134/S1063784217120271
  6. Isachenko V.P., Kushnyrev V.I. Jet cooling. Moscow, Energoatomizdat Publ., 1984, 216 p. (in Russian).
  7. Karpov P.A. Heat transfer during evaporative cooling of the surface with a multi-jet pulse spray. Diss. for the degree of Cand. Sci. (Engineering). Novosibirsk, 2021, 132 p. URL: https://www.nstu.ru/files/dissertations/dissertaciya_karpov_p.n._163427428270.pdf (accessed Jan.13, 2025) (in Russian).
  8. Koldin A.V., Platonov N.I. Heat transfer during jet cooling of a high-temperature surface. Bulletin of the Chelyabinsk State University. Physics. 2013;25:48–51. URL: https://elibrary.ru/contents.asp?id=33909325 (accessed Jan.13, 2025) (in Russian).
  9. Bratuta E.G. Heat transfer crisis during surface cooling with dispersed liquid. News of higher educational institutions. Power engineering. 1986;6:102–105 (in Russian).
  10. Kirillov P.L., Yuryev Yu.S., Bobkov V.P. Handbook of thermal hydraulic calculations (nuclear reactors, heat exchangers, steam generators). Moscow, Energoatomizdat Publ., 1990, 360 p. (in Russian).
  11. Yudov Yu.V., Volkova S.N., Migrov Yu.A. The Closing Relationships of the Thermohydraulic Model of the KORSAR Computer Code. Thermal Engineering. 2002;49(11):901–908.
  12. Yudov Yu.V. Numerical simulation of thermohydraulic processes in the circulation circuits of reactor installations with a water coolant. Diss. for the degree of Dr. Sci. (Phys.-Math.). Sosnovy Bor, 2021, 277 p. URL: https://www.ibrae.ac.ru/docs/108/yudovidissertatsiya.pdf (accessed Feb. 28, 2025) (in Russian).
  13. Bell K.J. Handbook of heat exchangers. In 2 volumes. Translation from English. Edited by O.G. Martynenko. Moscow, Energoatomizdat Publ., 1987, vol. 2, 352 p. (in Russian).
  14. ANSYS Fluent Theory Guide. ANSYS Inc., 2013, 814 p.
  15. Loktionov V.D. A method for cooling and protecting a nuclear reactor vessel in case of a severe accident and a device for its implementation. 2019, RF Patent No. RU 2743090 (in Russian).
  16. Soloviev S.L., Zaryugin D.G., Kalyakin S.G., Leskin S.T., Soloviev D.S. New Technical Solutions for the Design of NPP Passive Safety Systems. Nuclear Energy and Technology. 2024;10(4):251–257. DOI: https://doi.org/10.3897/nucet.10.139455

gas-droplet cooling of high-temperature surfaces heat transfer simulation system codes beyond-design-basis accident at high power NPPs application of air-droplet cooling in NPP safety systems

Link for citing the article: Zaryugin D.G., Leskin S.T., Mikhin S.A., Sergeev V.V., Slobodchuk V.I. On the Possibility of Cooling the High-Power VVER Reactor Pressure Vessel Using an Air-Droplet Spray in the Event of a Beyond Design Basis Accident. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 1, pp. 81-95; DOI: https://doi.org/10.26583/npe.2025.1.06 (in Russian).