EDN: YLFUME
Authors & Affiliations
Boldyrev A.M.1, Lyapin E.P.2, Seleznev E.F.3
1 Institute of Nuclear Physics and Engineering, National Research Nuclear University MEPhI, Moscow, Russia
2 Branch of Rosenergoatom Concern Joint Stock Company “Beloyarsk Nuclear Power Plant”, Zarechnyj, Russia
3 National Research Center “Kurchatov Institute“, Moscow, Russia
Boldyrev A.M. – Post-Graduate Student.
Lyapin E.P. – Head of JFL.
Seleznev E.F. – Leading Researcher, Dr. Sci. (Tech.). Contacts: 1, pl. Akademika Kurchatova, Moscow, Russia, 123182. Tel.: +7 (499) 196-92-57; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Abstract
Further work on the development of nuclear power plants in the country with fast neutron reactors with sodium coolant (BN) is associated with the implementation of measures leading to a reduction in the cost of supplied electricity. This can be achieved by modernizing the main design parameters of nuclear power plants: fuel, structural materials and coolant.
This paper examines some ways of such modernization related to the use of: original fuel assembly designs, in particular an axial layer of breeding material in the central part of the assembly along the height and metal fuel in the lower half of the reactor core; by introducing new structural materials for fuel cladding; as well as the possible use of a gas turbine instead of a steam turbine.
The need to use metallic fuel in a fast reactor, as the best type of fuel for it, including for economic reasons, was formulated at the dawn of the development of nuclear energy. However, if the problems with achieving deep combustion in such fuel were solved in practice, then the problems of feedback for high-power reactors remained unresolved until recently. In this paper, the use of metallic fuel in a high-power fast reactor (type BN-1200) is considered with the solution of the feedback problem in such a reactor.
Keywords
reduction of specific costs, fast reactors, BN-600, BN-800, BN-1200, associated with an increase in fuel burnup and the duration of the fuel assembly campaign and new reactor designs
Article Text (PDF, in Russian)
References
- Vasyaev A.V., Gulevich A.V., Diaghilev A.M. et al. AES s RU BN-1200M. Proyektno-konstruktorskiye resheniya, perekhod k ikh prakticheskoy realizatsii [NPP with RP BN-1200M. Designing Solutions, Practical Realization Stage]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2022, vol. 4, pp. 75–85.
- Frederic Serre et al. Generation-IV. French Atomic Energy Commissariat, IAEA. Vena, 2022.
- Drobyshev Yu.Yu., Seleznev E.F. Analiz kharakteristik bystrogo reaktora s metallicheskim toplivom [Analysis of the Characteristics of the Fast Breeder Reactor with Metallic Fuel]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2018, vol. 2, pp. 5–11.
- Drobyshev Yu.Yu., Seleznev E.F. Analysis of the Characteristics of the Fast Breeder Reactor with Metallic Fuel. Proc. of the International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Yekaterinburg, Russia, 26–29.06.2017. IAEA. CN245-188, 10 p.
- Seleznev E.F., Drobyshev Yu.Yu. Teplovydelyayushchiy element yadernogo energeticheskogo reaktora na bystrykh neytronakh [Fuel element of a fast neutron nuclear power reactor]. Patent for invention RF № 2680252, 19.02.2019.
- Drobyshev Yu.Yu., Seleznev E.F. Hybrid high power fast reactor with metallic fuel and additives consisting with lightweight atims. International Conference on Fast Reactors and Related Fuel Cycles: Sustainable Clean Energy for the Future (FR22), Vienna, Austria, 19–22.4.2022, IAEA.
- Golovchenko Yu.M. Some results of Developments and Investigations of Fuel Pins with Metal Fuel for Heterogeneous Core of Fast Reactors of the BN-type. Energy Procedia, 2011, vol. 7, pp. 205–212.
- Carmack W.J., Porter D.L., Chang S.L. et al. Metallic fuels for advanced reactors. Journal of Nuclear Materials, 2009, vol. 392, issue 2, pp. 139–150.
- Eliseev V.A., Matveev V.I. Optimizatsiya geterogennoy aktivnoy zony s aksial'noy prosloykoy [Optimization of a heterogeneous core with an axial layer]. Doklad na sovetsko-yaponskiy seminare [Report at the Soviet-Japanese seminar]. IPPE, Obninsk, 16.06.87, 9 p.
- Poplavskii V.M., Tsibulya A.M., Khomyakov Y.S. et al. Core and fuel cycle for an advanced sodium-cooled fast reactor. At Energy, 2010, vol. 108, issue 4, pp. 260–266. DOI: https://doi.org/10.1007/s10512-010-9287-y.
- Kamei T., Jamaoka M., Moriki Y. et al. An Axially and Radially Two-zoned Large LMFBR Core Concept. Nucl. Technology, 1985, vol. 71, no. 3, p. 548.
- Seleznev E.F., Drobyshev Yu.Yu., Karpov S.A. et al. Solution of the Equations of Nuclide Kinetics. At Energy, 2021, vol. 130, pp. 262–266. DOI: https://doi.org/10.1007/s10512-021-00806-8.
- Bobkov V.P., Blochin V.N., Rumyantsev V.А. et al. Spravochnik po svoystvam materialov dlya perspektivnykh reaktornykh tekhnologiy. Tom 5. Svoystva reaktornykh staley i splavov. Pod redaktsiyey V.M. Poplavskogo [Handbook of Material Properties for Advanced Reactor Technologies. V.5. Properties of reactor steels and alloys. Ed. V.M. Poplavsky]. Moscow, IzdAT Publ., 2011-, 2014. 582 p.
- Nikitina A.A., Ageev V.S., Leont’eva-Smirnova M.V. et al. Advances in Structural Materials for Fast-Reactor Cores. At Energy, 2016, vol. 119, pp. 362–371. DOI: https://doi.org/10.1007/s10512-016-0074-2.
- Ageev V.C., Budanov Y.P., Ioltuchovsky A.G. et al. Konstruktsionnyye materialy aktivnykh zon rossiyskikh bystrykh reaktorov. Sostoyaniye i perspektivy [Structural materials of the active zones of Russian fast reactors. Status and prospects]. Izvestiya vuzov. Yadernaya Energetika, 2009, no. 2, pp. 210–218.
- Agranovich V.М., Kirsanov V.V. Problemy modelirovaniya radiatsionnykh povrezhdeniy v kristallakh. [Problems of modeling radiation damage in crystals]. Uspekhi fizicheskikh nauk – Advances in Physical Sciences, 1976, vol. 118, no. 1, p. 3.
- Norgett M.J., Robinson M.T., Torrens I.M. A Proposed Method of Calculating Displacement Dose Rates. Nuclear Engineering and Design, 1975, vol. 33, p. 50.
- Morgan W.C. Atomic displacement cross section for carbon from ENDF/B-III data. Journal of Nuclear Materials, 1974, vol. 51, p. 209.
- Avramenko V.I., Konobeev Y.V., Strokova A.M. Neutron cross sections for the calculation of the damaging dose in reactor materials. At Energy, 1984, vol. 56, pp. 144–147. DOI: https://doi.org/10.1007/BF01131454.
- Zabrodskaya S.V., Ignatyuk A.V., Koshcheev V.N. et al. ROSFOND – rossiyskaya natsional'naya biblioteka otsenennykh neytronnykh dannykh [RUSFOND – Russian National Library of Evaluated Neutron Data]. Voprosy atomnoy nauki i tekhniki. Seriya: Yadernyye konstanty – Problems of Atomic Science and Technology. Series: Nuclear Constants, 2007, vol. 1–2.
- Tebin V.V., Sinica V.V., Osadchii A.I. et al. Kompleks programm i bibliotek konstant SAPFIR-2006. [Complex codes and library constant SAPFIR-2006]. Certificate code passport No. 251. Moscow,
FECETAN, NTC JARB Publ., 2008. 6 p.
- Gokhshtein D.P., Verkhivker G.P. Use of carbon dioxide as a heat carrier and working substance in atomic power stations. At Energy, 1969, vol. 26, issue 4, pp. 430–432. DOI: https://doi.org/10.1007/BF01371881.
- Chris Grandy. Fast Reactor Technology. Argonne National Laboratory Presentation to GAO U.S. Departament of Nuclear Energy, 2007, May 24.
- Rochau G.E. Supercritical CO2 Brayton Cycle. Development Nuclear Energy Advisory Committee Brifing U.S., Departament of Nuclear Energy, 2014, June 5.
- Solovyov S.L. Osnovnyye tendentsii razvitiya mirovogo reaktorostroyeniya i svyazannyye s nim teplofizicheskiye problemy [Main trends in the development of global reactor construction and related thermophysical problems]. Saint Petersburg, SPPU, 24.05.2017, 20 p.
UDC 621.039.553
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 3, 3:6
