Autonomous Thermosiphon System of Passive Residual Heat Removal from the Primary Circuit of the Reactor Plant: Features of Operation, Characteristics and Basic Advantages
https://doi.org/10.21122/1029-7448-2023-66-5-433-450
Abstract
An autonomous system of passive removal of residual heat (PRRHS) of a reactor installation with VVER designed to ensure the safety of nuclear power plants in an accident with complete long-term blackout is considered. The system provides for the removal of heat directly from the first circuit of the reactor plant (PRRHS R). In order to increase the reliability and safety of the emergency heat sink, heat exchange equipment based on closed-type evaporation and condensation devices – two-phase thermosyphons – has been used in the system. The main feature of such heat exchangers is that their thermosiphon assemblies structurally separate the primary circuit and the auxiliary circuit of the PRRHS, which is removed outside the reactor compartment, and provide safe and efficient heat removal, reduce the risk of radioactive contamination spreading beyond safety barriers. Such autonomous passive systems will provide effective heat removal directly from the primary circuit by changing the chain of successive heat transfer sites from nuclear fuel to the final absorber and excluding from it such elements, as for example steam generators, the condition and operability of which in the emergency process of heat removal have a major impact on the safety of the reactor core. The article presents a diagram of an autonomous heat sink system; also, a description of its operation is given. The main characteristics of the course of the emergency process of removal of residual heat by the autonomous thermosiphon PRRHS R obtained by computational modeling have been considered. The advantages of an autonomous thermosiphon passive system in comparison with a passive heat removal system of a reactor installation with VVER through the second circuit are analyzed. The obtained results are proposed to solve the problems of diversification of passive safety systems of evolutionary reactor plants of nuclear power plants with VVER type reactors.
About the Authors
I. I SviridenkoRussian Federation
Address for correspondence:
Sviridenko Igor I. -
Sevastopol State University,
33, University st.,
299053, Sevastopol, Russian Federation.
Tel.: +7 978 704-68-74
i.sviridenko@mail.ru
D. V. Shevelyov
Russian Federation
Moscow
References
1. Bukrinskii A. M. (2019) Safety of Nuclear Power Plants According to Federal Norms and Regulations of Russia and IAEA Standards. Comparison of Basic Principles and Requirements for Ensuring Safety. Third Edition. Moscow, STC NRS. 196 (in Russian).
2. Dmitriev S. M., Gerasimov A. V., Dobrov A. A., Doronkov D. V., Pronin A. N., Ryazanov A. V., Solntsev D. N., Khrobostov A. E. (2020) Investigation of Coolant Local Hydrodynamics in the Mixed Core of the VVER Reactor. Energetika. Izvestiya Vysshikh Uchebnykh Zavedenii i Energeticheskikh Ob’edinenii SNG = Energetika. Proceedings of the CIS Higher Education Institutions and Power Engineering Associations, 63 (2), 151–162. https://doi.org/10.21122/1029-7448-2020-63-2-151-162 (in Russian).
3. Sorokin V. V. (2022) Calculation of Start-Up Time of Passive Catalytic Hydrogen Recombiner of Localization Safety System of a Nuclear Power Plant Equipped with VVER. Energetika. Izvestiya Vysshikh Uchebnykh Zavedenii i Energeticheskikh Ob’edinenii SNG = Energetika. Proceedings of the CIS Higher Education Institutions and Power Engineering Associations, 65 (1), 67–75. https://doi.org/10.21122/1029-7448-2022-65-1-67-75 (in Russian).
4. Morozov A. V., Ragulin S. V., Sahipgareev A. R., Shlepkin A. S. (2018) Ways to Improve the Passive Cooling System of the VVER Reactor Core. Problemy Sovershenstvovaniya Toplivno-Energeticheskogo Kompleksa. Materialy XIV Mezhdunarodnoi Nauch.-Tehn. Konf., Saratov, 30 Oktyabrya – 1 Noyabrya 2018 g. [Materials of the XIV International Scientific and Technical Conference “Problems of Improving the Fuel and Energy Complex”]. Saratov, 115–120 (in Russian).
5. IAEA (2009) Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants: IAEA-TECDOC-1624. Vienna. Available at: https://www-pub.iaea.org/MTCD/Publications/PDF/te_1624_web.pdf (аccessed 07 January 2022).
6. IAEA (2005) Natural Circulation in Water Cooled Nuclear Power Plants: Phenomena, Models, and Methodology for System Reliability Assessments. IAEA-TECDOC-1474. Vienna. Available at: https://www-pub.iaea.org/MTCD/Publications/PDF/TE_1474_web.pdf (аccessed 05 January 2022).
7. Sierchuła J. (2019) Analysis of Passive Residual Heat Removal System in AP1000 Nuclear Power Plant. IOP Conference Series: Earth and Environmental Science, 214, 012095 https://doi.org/10.1088/1755-1315/214/1/012095.
8. Li F., Lu Y., Chu X., Zheng Q., Wu G. (2021) Design, Experiment, and Commissioning of the Passive Residual Heat Removal System of China’s Generation III Nuclear Power HPR1000. Science and Technology of Nuclear Installations, 2021, 6680400. https://doi.org/10.1155/2021/6680400.
9. Dunn P. D., Reay D. A. (1982) Heat Pipes. Elsevier Science & Technology Books.
10. Chi S. W. (1976) Heat Pipes: Theory and Practice. Hemisphere Pub. Corp.
11. Gershuni O. N., Nishchik O. P., Pishmennyi E. M. (2007) Evaporation-Condensation Heat Transfer Systems for Nuclear Energy Technologies. Kyiv, Al'terpres Publ. 236 (in Ukrainian).
12. Vijayan P. K., Nayak A. K., Kumar N. (2019). Chapter 1 – Natural Circulation Loops – Advantages, Challenges, and Classification. Single-Phase, Two-Phase and Supercritical Natural Circulation Systems. Woodhead Publishing, 1–30. https://doi.org/10.1016/B978-0-08-102486-7.00001-9.
13. Sviridenko I. I., Shevelyov D. V., Polyakov O. V., Timofeev V. A., Sviridenko N. N. (2015) Passive Residual Heat Removal System for WWER with the Thermosiphon Heat Exchange Equipment. International Journal of Energy for a Clean Environment, 16 (1–4), 209–223. https://doi.org/10.1615/InterJEnerCleanEnv.2015015683.
14. Sviridenko I. I., Shevelev D. V., Sverdlov V. V. (2018) Analytical Researches of Emergency Heat Removal from VVER by Autonomous Thermosyphon PRHRS of Primary Circuit. Tehnologii Obespecheniya Zhiznennogo Tsikla Yadernyh Energeticheskikh Ustanovok: Nauch.-Tehn. Sbornik = Nuclear Propulsion Reactor Plants. Life Cycle Management Technologies. Collection of Scientific and Technical Papers. Sosnovy Bor: FSUE “Alexandrov NITI”, Iss. 3(13), 28–41 (in Russian).
15. Sviridenko I. I. (2019) Assuring Reactor's Subcriticality Following Beyond Design Accident by Simultaneous Cool Down and Depressurization. Izvestiya Vuzov. Yadernaya Energetika, (1), 85–96 (in Russian). https://doi.org/10.26583/npe.2019.1.08.
16. Zaporozhye NPP (2017) Instructions for the Elimination of Accidents and Emergencies at the Reactor Plant of Power Unit No 5 of the Zaporozhye NPP. 05.ГТ.00.ИЭ.11 (in Russian).
17. Vasiliev L. L. (1981) Heat Exchangers on Heat Pipes. Minsk, Nauka i Tehnika Publ. 143 (in Russian).
18. Bezrodnii M. K., Pioro I. L., Kostyuk T. O. (2005) Transfer Processes in Two-Phase Thermo-siphon Systems. Theory and Practice. Kyiv, Fakt Publ. 704 (in Russian).
19. Atomenergoproekt (2002) Kudankulam NPP. Classification of Systems, Equipment, Pipelines and Elements of the Heat Engineering Division. KK.UJA.0.SR.PZ.PR004 (in Russian).
20. Blagoveshchenskii A. Ya., Bor S. M., Konovich M. N., Mityukov V. N., Bezlepkin V. V., Kukhtevich V. O., Mitryukhin A.G. [et al.] (2012) The Concept of Expanded Use of Natural Circulation of the Primary Coolant in Power Units with VVER-1000 (1200) and Prospects for its Implementation. Bezopasnost', Effektivnost' i Ekonomika Atomnoi Energetiki: Materialy 8 Mezhdunar. Nauch.-Tehn. Konf., Moskva, 23–25 Maja 2012 g. [Safety, Efficiency and Economy of Nuclear Energy: Proceedings of the 8th Intern. Sci.-Tech. Conf.]. Moscow, Rosenergoatom Concern, 602–605 (in Russian).
21. Bukin N. V., Borisov L. N., Gromov A. L., Fil N. S., Shumskii A. M. (2001) Influence of Passive Systems on the Course of Typical Beyond Design Basis Accidents of V-392 Reactor Plant. Obespechenie Bezopasnosti AES s VVER: Materialy 2 Nauch.-Tehn. Konf., Podol'sk, 19–23 Noyabrya 2001 g. [Ensuring the Safety of VVER NPP: Proceedings of the 2nd Sci.-Tech Conf.]. Available at: http://www.gidropress.podolsk.ru/files/proceedings/mntk2001/report1/vpsnptza.pdf (аccessed 17 September 2021) (in Russian).
22. Andrushechko S. A., Afrov A. M., Vasiliev B. Yu., Generalov V. N., Kosourov K. B., Semchenkov Yu. M., Ukraintsev V. F. (2010) NPP with a VVER-1000 Reactor. From the Physical Fundamentals of Operation to the Evolution of the Project. Moscow, Logos Publ. 603 (in Russian).
Review
For citations:
Sviridenko I.I., Shevelyov D.V. Autonomous Thermosiphon System of Passive Residual Heat Removal from the Primary Circuit of the Reactor Plant: Features of Operation, Characteristics and Basic Advantages. ENERGETIKA. Proceedings of CIS higher education institutions and power engineering associations. 2023;66(5):433-450. (In Russ.) https://doi.org/10.21122/1029-7448-2023-66-5-433-450