I. G. Sharaevsky, N. M. Fialko, L. B Zimin, A. V. Nosovskyi, T. S. Vlasenko,
G. I. Sharaevsky
Institute for Safety Problems of Nuclear Power Plants, NAS of Ukraine, 12, Lysogirska st., Kyiv, 03028, Ukraine
DOI: doi.org/10.31717/2311-8253.20.2.1
Abstract
The article is devoted to critical review of the state of theoretical and experimental scientific researches, creation of calculation methods and concepts, as well as development of conceptual pilot projects of channel and tank water cooled reactors with supercritical pressure of coolant (SCWR) in the USA, Canada, Japan, Germany, and more. Russian projects for such reactors are to be considered individually in the future. The main technical and economic characteristics of these projects are presented and compared in a generalized way. Advantages and disadvantages of the transition to the single-circuit scheme of circulating coolant with nuclear overheating of steam in realization of different variants of working fluid movement organization are estimated in these projects. Known forecasts for the reduction of capital and operating costs for the construction and operation of power units up to 1,200 MW (el) are analyzed for the concepts of fast, thermal and mixed neutron spectrums in the core. Insufficient validity issues of heat exchange processes safety on the surface of fuel elements in the core is revealed, in particular, taking into account the possibility of a potentially dangerous phenomenon of its fluid pseudo-boiling in the conditions of supercritical parameters of the coolant. The necessity to carry out an additional set of appropriate bench of experimental studies was emphasized in order to increase the reliability of the expected technical and environmental safety indicators.
Keywords: water-cooled energy reactor, circuit of coolant circulation, supercritical parameters.
References
1. Energy Strategy of Ukraine for the period up to 2035 «Safety, Energy Efficiency, Competitiveness». Approved by the CMU of 18.08.2017, no. 605-p., 66 p. Available at: http//inpe.kmu. gov.ua/ minugol/doccatalog/document?id=245239554 (in Ukr.)
2. Kirillov P. L. (2013). Vodookhlazhdaemyi reaktor VVER-SKD (predvaritel’nye razrabotki) [Water-cooled VVER-
SCP reactor (preliminary developments)]. Izvestiya VU-Zov. Yadernaya energetika [University News. Nuclear power], no. 1, pp. 11-13. (in Russ.)
3. Azarenkov N. A., Bulavin L. A., Zaliubovsky I. I., Kirichenko V. G., Nekliudov I. M., Shiliaev B. A. (2012). Yadernaya energetika: uchebnoe posobie [Nuclear Energy: A Tutorial]. Kharkiv: V. N. Karazin Kharkiv National University, 480 p. (in Russ.)
4. Baranaev Yu. D., Kirillov P. L., Klushin A. V. (2010). Reaktor, okhlazhdaemyi vodoi sverkhkriticheskogo davleniya, VVER SKD — osnovnoipretendent v “Super-VVER” [Supercritical water cooled reactor, VVER SCP — the main contender in Super-VVER]. Preprint FEI-3188, pp. 29-35. (in Russ.)
5. Supercritical Water-cooled Reactor. Report of SCWR System Steering Committee. Proceedings of the 12th INPRO Dialogue Forum (Vienna, Austria, April 13-15,2016), p. 66.
6. GIF R&D Outlook for Generation IV Nuclear Energy Systems (August 21, 2009), p. 32.
7. Sinev N. M., Baturov B. B. (1980). Ekonomika atomnoy energetiki [Economics of nuclear energy]. In: Osnovy tekhnologii i ekonomiki proizvodstva jadernogo topliva [Fundamentals of technology and economics of nuclear fuel production]. Moscow: Atomizdat. (in Russ.)
8. Alekseev P. et al. (2015). Conceptual Proposals on Reactor VVER-SCW Developed on the Basis of Technologies of VVER and Steam-Turbine Installations at Supercritical Parameters. Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors ISSCWR-7 (Helsinki, Finland, March 15-18, 2015). Report ISSCWR7-No2055.
9. Schulenberg T., Starflinger J. (eds.) (2012). High Performance Light Water Reactor. Design and Analyses. Karlsruhe: KIT Scientific Publishing, 242 p. Available at: https://pdfs. semanticscholar.org/a112/3c4de154ad4367146db09b-337930de020b76.pdf.
10. Yetisir M., Diamond W., Leung L. K. H., Martin D., Duffey R. (2011). Conceptual Mechanical Design for a Pressure-Tube Type Supercritical Water-Cooled Reactor. Proceedings of the 5th International Symposium on Supercritical Water-cooled Reactors (Vancouver, Canada, March 13-17, 2011).
11. Pioro I. L., Duffey R. B. (2007). Heat transfer and hydraulic resistance at supercritical pressures in power-engineering applications. New York: ASME Press, 334 p.
12. Makhin V. M., Mokhov V. A., Berkovich V. Ya., Nikiten-ko M. P., Churkin A. N., Lapin A. V., Kirillov P. L., Baranaev Yu. D., Glebov A. P. (2015). Conceptual proposals on VVER-SCP reactor prototype [Kontseptual’nye pred-lozheniya po stendu-prototipu reaktora VVER-SKD]. Tyazheloe mashinostroenie [Heavy engineering], no. 7-8, p. 45-51. (in Russ.)
13. Baranaev Y. D., Glebov A. P., Kirillov P. L. (2013). Neutron-ic Characteristics of 30 MWt SCW Experimental Reactor. Report ISSCWR-2013. Proceedings of the ISSCWR-2013 (China, Shenzhen, March, 2013).
14. Buongiorno J., MacDonald P. E. (2003). Supercritical Water Reactor (SCWR). Progress Report for the FY-03 Generation-IV R&D Activities for the Development of the SCWR in the U.S., INEEL/EXT-03-01210. INEEL, 2003, 38 p.
15. MacDonald P. E., Buongiorno J., Davis C., Witt R. (2003). Feasibility Study of Supercritical Light Water Cooled Reactors for Electric Power Production. Progress Report for Work Through September 2003 2nd Annual Report and 8th Quarterly Report INEEL/EXT-03-01277. INEEL, 2003, 138 p.
16. Маkhin V. М., Churkin А. N. (2017). Kontseptual’nye pred-lozheniya po vodookhlazhdaemomu reaktoru so sverkhkri-ticheskimi parametrami [Conceptual proposals for a water-cooled reactor with supercritical parameters]. Voprosy atomnoi nauki i tekhniki. Ser.: Fizikayadernykh reaktorov [Problems of Atomic Science and Technology. Ser.: Physics of Nuclear Reactors], no. 1, pp. 48-65. (in Russ.)
17. Мikhan V. I., Мstiaev Yu.I., Zvereva G. А. (1978). Kanal’nye vodno-graphiovye reaktory s peregrevom para [Channel water-graphite reactors with superheating vapor]. Voprosy atomnoi nauki i tekhniki. Ser.: Fizika yadernykh reaktorov
[Problems of Atomic Science and Technology. Ser.: Physics of Nuclear Reactors] vol. 21, no. 1, рp. 68-73. (in Russ.)
18. Baturov B. B., Koriakin Yu. I., Smirnov V. G. (1978). Op-timizacionnye tekhniko-modeli reaktornykh ustanovok tipa RBM-K i RBM-KP [Optimization technical models of RBM-K and RBM-KP reactor plants]. Voprosy atomnoi nauki i tekhniki. Ser.: Fizika yadernykh reaktorov [Problems of Atomic Science and Technology. Ser.: Physics of Nuclear Reactors], vol. 21, no. 1, рp. 79-91. (in Russ.)
19. Vikulov V. K., Gmyrko V. Ye., Grozdov I. I., et al. (2007). VGERS — Supercritical Water-Cooled GraphiteModerated Power Reactor. Proceedings of the “Advanced Nuclear fuel cycle for the 21st century” (Nizhny Novgorod, Russia, September 24-27, 2007), p. 104.
20. Zhang W. (2013). Preliminary Core Conceptual Design of 1000 MWe SCWR. Report 13066. Proceedings of the 6th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-6) (Shenzhen, China, March 3-7, 2013).
21. Chow C. K., Khartabil H. F. (2007). Conceptual fuel channel designs for CANDU-SCWR. Nuclear Engineering and technology, vol. 40, no. 2, pp. 139.
22. Leung L. (2013). Overview of SCWR Concepts. In: IAEA-SJTU Course on Science and Technology of SCWRs. Shanghai, China, 2013.
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