EDN: YYNXLW
Authors & Affiliations
Sedov A.A.1, Pustovalov S.B.1, Kotov Ya.A.1, Lapin A.S.1, 2, Nevinitsa V.A.1, Subbotin S.A.1, Fomichenko P.A.1
1 National Research Center “Kurchatov Institute”, Moscow, Russia
2 National Research Nuclear University MEPhI Moscow Engineering Physics Institute, Moscow, Russia
Sedov A.A.1 – Division Deputy Director.
Pustovalov S.B.1 – Head of Department, Cand. Sci. (Tech.).
Kotov Ya.A.1 – Senior Researcher.
Nevinitsa V.A.1 – Division Director, Cand. Sci. (Tech.).
Subbotin S.A.1 – Head of Department, Cand. Sci. (Tech.).
Fomichenko P.A.1 – Complex Deputy Director.
Lapin A.S.1, 2 – Senior Researcher. Contacts: 1, pl. Akademika Kurchatova, Moscow, Russia, 123182. Tel.: +7 (499) 196-71-42; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
The article formulates the system requirements for VVER-SCP reactors based on the analysis of scenarios for the development of Russian Nuclear Energy. A brief description of the VVER-SCP reactor, features of its physics and design, features of the cluster control and protection system of the reactor, and core fuel are given. The indicators of the reactor's nuclear fuel cycle, indicators of breeding of secondary nuclear fuel (fissile isotopes of plutonium), the main coefficients and effects of reactivity are presented. A brief description of the nuclear power installation with this reactor is given, the features of the reactor and steam turbine systems of the nuclear power installation are presented. The comparison of specific indicators of nuclear power units based on light-water reactors AES-2006 and AP-1000 with specific indicators of the VVER-SCP power unit is also given. The article presents the main provisions of the concept of the multi-purpose low-power test research reactor MTIR-SCP, as the main experimental research base for testing VVER-SCP technologies. The main characteristics and features of the neutron physics of the MTIR-SCP are given, the features of its operation and the possibilities for conducting reactor experiments and irradiations are presented. Brief results of VVER-SCP developments in the period 2019-2023 are also presented. A list of necessary R&D in support of the MTIR-SCP and VVER-SCP projects and a roadmap for the development of the VVER-SCP direction before the creation of a pilot demonstration power unit by 2050 is provided.
Keywords
light-water coolant, supercritical parameters, power reactor, VVER-SCP, reactivity coefficients, thermal hydraulics, neutron physics, fuel cycle, nuclear power system
Article Text (PDF, in Russian)
References
- PRIS (Power Reactor Information System). Available at: https://pris.iaea.org/PRIS/CountryStatistics/CountryDetails.aspx?current=RU (accessed 12.01.2023).
- Asmolov V.G., Zrodnikov A.V., Solonin M.I. Innovative development of nuclear power in Russia. At Energy, 2007, vol. 103, issue 3, pp. 665–674. DOI: https://doi.org/10.1007/s10512-007-0107-y.
- Semchenkov Yu.M., Sidorenko V.A., Sedov A.A. et al. Kontseptual'nyye predlozheniya po reaktoru VVER-SKD, sozdavayemomu na osnove tekhnologiy VVER i paroturbinnykh ustanovok na SKD parametrakh [Conceptual proposals for the VVER-SCP reactor, created on the basis of VVER technologies and steam turbine installations based on SCP parameters]. Sbornik trudov 9-y mezhdunarodnoy nauchno-tekhnicheskoy konferentsii “Obespecheniye bezopasnosti AES s VVER” [Proceedings of the 9th International Scientific and Technical Conference “Ensuring the safety of Nuclear Power plants with VVER”]. Podolsk, Russia, May 19–22, 2015.
- Alekseev P.N., Kovalishin A.A., Sedov A.A. et al. Razvitiye tekhnologii VVER na baze energeticheskikh reaktorov s legkovodnym teplonositelem sverkhkriticheskikh parametrov [Development of VVER technology based on power reactors with a light-water coolant of supercritical parameters]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2023, issue 1, pp. 49–63.
- Reporting materials of the mining division for 2019. ARMZ/Rosatom. Available at: https://report.rosatom.ru/go/atomredmetzoloto/go_atomredmetzoloto_2019/armz_2019.pdf (accessed 08.05.2024).
- Alekseev P.N., Kormilitsyn M.V., Kormilitsyna L.A. et al. NFC Russia Infrastructure Readiness
Assessment for Development of PSKD-600 Power Reactors. At Energy, 2021, vol. 130, pp. 1–5. DOI: https://doi.org/10.1007/s10512-021-00764-1.
- Kormilitsyn M.V., Kormilitsyna L.A., Pustovalov S.B. et al. Techno-Economic Prognosis for the Manufacture of Fuel Assemblies with Mixed Uranium-Plutonium Fuel for the VVER-SKD Power Reactor. At Energy, 2022, vol. 132, pp. 143–148. DOI: https://doi.org/10.1007/s10512-023-00917-4.
- Alekseev P.N. et al. A fast reactor with a high excess operating time of fissile nuclides in two-component nuclear power with a U-Pu and Th-U-Pu fuel cycle. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2020, no. 5. pp. 53–65.
- Adamov E.O., Asmolov V.G., Bolshov L.A., Ivanov V.K. Dvukhkomponentnaya yadernaya energetika [Two-component Nuclear Power]. Vestnik RAN – Bulletin of the Russian Academy of Sciences, 2021, vol. 91, no. 5, pp. 450–458.
- Zorin V.M., Shamarokov A.S., Pustovalov S.B. The New Generation of High-Pressure Heaters for Steam Turbine Units at Nuclear Power Plants. Therm. Eng., 2021, vol. 68, issue 4, pp. 285–294. DOI: https://doi.org/10.1134/S004060152104008X.
- Shamarokov A.S., Zorin V.M., Pustovalov S.B. et al. The New Generation of Moisture Separators-Reheaters for Steam-Turbine Units of Nuclear Power Plants (NPP) with VVER-Reactors. Therm. Eng., 2022, vol. 69, pp. 691–701. DOI: https://doi.org/10.1134/S0040601522080080.
- Kotov Ya.A., Kolesov V.V., Nevinitsa V.A., Fomichenko P.A. Issledovaniye effektov reaktivnosti i drugikh neytronno-fizicheskikh kharakteristik VVER-SKD [Investigation of the effects of reactivity and other neutron-physical characteristics of VVER-SCP]. V sb.: Tezisy dokladov konferentsii “Neytronika-2022 [Proc. of the Conference “Neutronics-2022”]. Obninsk, 2022, pp. 38–39.
- Pisarev A.N., Kolesov V.V., Kotov Ya.A., Nevinitsa V.A., Fomichenko P.A. Ob otsenke neopredelennostey yadernykh kontsentratsiy minornykh aktinidov pri raschetakh vygoraniya topliva v TVS reaktora VVER-SKD [On the assessment of uncertainties of nuclear concentrations of minor actinides in calculations of fuel burnout in the fuel assemblies of the VVER-SCP reactor]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, issue 4, pp. 35–45.
- Vnukov R.A., Kotov Ya.A., Nevinitsa V.A. et al. Otsenka vozmozhnosti polucheniya eksperimental'nykh dannykh dlya zon VVER-SKD na stende BFS [Evaluation of the Possibility of Performing an Experiment for VVER-SKD Zones at the BFS Facility]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2023, issue 1, pp. 117–129.
- Sedov A.A., Blandinskii V.Yu., Kotov Ya.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., 2023, vol. 70, issue 5, pp. 323–338. DOI: https://doi.org/10.1134/S0040601523050063.
- Lapin A.S., Blandinsky V.Yu. Obosnovaniye vybora moshchnosti mnogotselevogo testovogo issledovatel'skogo reaktora so sverkhkriticheskimi parametrami legkovodnogo teplonositelya [Justification for choosing the power of a multipurpose test research reactor with supercritical parameters of a light-water coolant]. Tezisy dokladov konferentsii “Bezopasnost' AES i podgotovka kadrov” [Proc. of the conference “NPP safety and Personnel Training”]. Obninsk, October 26–27, 2023. Obninsk: Optima-Press LLC Publ., 2023. Pp. 78–79.
- Semchenkov Yu.M., Silin V.A., Alekseev P.N., Chibinyaev A.V., Mitkin V.V., Khlopov R.A. Integral'nyye reaktornyye ustanovki s yestestvennoy tsirkulyatsiyey vody pri sverkhkriticheskom davlenii – RU SKDI [Integrated reactor installations with natural water circulation at supercritical pressure – RI SKDI]. Sb. trudov konferentsii “Obespecheniye bezopasnosti AES s VVER” [Proc. of the conf.;”Ensuring the Safety of NPP with VVER”]. Podolsk, OKB Gidropress, 2015, pp. 198–214.
- Glebov A.P., Baranaev Yu.D., Moskovchenko I.V., Kirillov P.L. SCWR Development From Concept to Test Reactor. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2019, no. 3, pp. 30–44.
- Sedov A.A., Polyakov P.S., Pustovalov S.B. et al. Main Results of the Trial Test of a Closed Circuit with Natural Circulation of a Light-Water Coolant under Supercritical Pressure. Therm. Eng., 2023, vol. 70, issue 3, pp. 223–235. DOI: https://doi.org/10.1134/S0040601523030072.
- Zakharko Yu.A., Stepanov A.S., Sedov A.A. Analiticheskiye resheniya termovyazkouprugikh uravneniy dlya tsilindricheskikh tel primenitel'no k prognozirovaniyu povedeniya tvelov energeticheskikh reaktorov [Analytical solutions of thermoviscoelastic equations for cylindrical bodies in relation to predicting the behavior of fuel rods of power reactors]. Voprosy atomnoy nauki i tekhniki. Seriya: Fizika yadernykh reaktorov – Problems of Atomic Science and Technology. Series: Physics of Nuclear Reactors, 2021, issue 1, pp. 55–63.
UDC 621.039, 539.1
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 2, 2:11
