EDN: EUZJNE
Authors & Affiliations
Zhirnov A.P., Davydov V.K., Moiseev A.V., Soldatov E.O., Khakhulin V.I.
N.A. Dollezhal Research and Development Institute of Power Engineering, Moscow, Russia
Zhirnov A.P. – Head of Department.
Davydov V.K. – Senior Researcher.
Moiseev A.V. – Scientific Supervisor of the BREST-OD-300 Project, Cand. Sci. (Phys.-Math.).
Soldatov E.O. – Head of Group. 1, bld.3, pl. Akademika Dollezhalya, Moscow, Russia, 107140. Tel.: +7 (499) 763-04-57; e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Khakhulin V.I. – Engineer of the 2nd Category.
Abstract
The paper considers fuel composition options using the BR-1200, BN-1200M starting load, the BN-800 blanket, the VVER MOX spent nuclear fuel and the VVER spent nuclear fuel plutonium to confirm the operation of the reactor in an equilibrium mode with a low reactivity margin. Calculations and research of the effect on the neutron-physical characteristics of the reactor by the considered fuel compositions were performed. The fuel density and the mass fraction of plutonium are adjusted when the isotopic composition of plutonium changes. The calculations of the neutron-physical characteristics and campaign at the initial stage of the BR-1200 reactor operation were carried out using the MCU-BR and FACT-BR programs. Changing isotopic composition of BR-1200 plutonium to isotopic compositions of other variants leads to redistribution of absorption and fission rates among plutonium isotopes. Since the reactivity weights of isotopes 238Pu, 239Pu, 240Pu, 241Pu, 242Pu have different values, the course of reactivity in the campaign differs for different variants of the isotopic composition of plutonium. As part of the simulation of the reactor campaign with the researched fuel compositions, the fuel assembly reload scheme was determined at the initial stage of operation. The fuel density and the mass fraction of plutonium in the loaded fuel were selected to ensure a reactivity margin within 1 βeff and the order of permutation and replacement of permanent reactivity control absorbers was determined. The research was conducted on the dependence of reactivity margin on fuel storage duration. It was concluded that for the isotopic composition from the BN-1200M, the VVER MOX spent nuclear fuel and the VVER spent nuclear fuel it is necessary to adhere to the panned dates for the reactor start-up and reactor commissioning. For the initial core load of the BR-1200 and the BN-800 blanket the reactivity margin can be maintained within 1 βeff by using permanent reactivity control absorbers.
Keywords
BR-1200 reactor, neutron-physical calculation, lead coolant, isotopic composition of plutonium, fast reactor fuel
Article Text (PDF, in Russian)
References
- Balovnev A.V., Davydov V.K., Zhirnov A.P., Moiseev A.V., Soldatov E.O. Modelling of Closed Fuel Cycle of the Lead-Cooled Fast Reactor. Izvestiya vuzov. Yadernaya Energetika, 2021, no. 4, pp. 66–75. DOI: https://doi.org/10.26583/npe.2021.4.06.
- Adamov E.O., Kaplienko A.V., Orlov V.V., Smirnov V.S., Lopatkin A.V., Lemekhov V.V., Moiseev A.V. Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation. At Energy, 2021, vol. 129, issue 4, pp. 179–187. DOI: https://doi.org/10.1007/s10512-021-00731-w.
- Rachkov V.I., Adamov E.O., Lopatkin A.V., Pershukov V.A., Troyanov V.M. Fast Reactor Development Programm in the Russian Federation (FR 13). Proc. of the International Conference Fast Reactors and Related Fuel Cycles: Safe Technologies and Sustainable Scenarios. Paris, France. March 4, 2013, pp. 93–102.
- Adamov E.O., Filin A.I., Orlov V.V. Nuclear power development on the basis of new nuclear reactor and fuel cycle concepts. Proc. of the Conf. on Innovative Technologies for Nuclear Fuel Cycles and Nuclear Power. Vienna, June 23–26, 2003. Report IAEA-CN-108/32. Pp. 243–257.
- Apse V.A., Shmelev A.N. Yadernye tekhnologii. Uchebnoe posobie [Fundamentals of safe radioactive waste management. Tutorial]. Moscow, MIFI Publ., 2008. 128 p.
- Rodina E.A., Egorov A.V., Rachkov V.I., Khomiakov I.S. Modeling and comparative analysis of changeover of homogeneous and heterogeneous core of BN-1200 reactor to equilibrium mode. Nuclear Engineering and Design, 2022, vol. 386, p. 111549.
- Balovnev A.V., Davidov V.K., Zhirnov A.P., Ivanyuta A.N., Moiseev A.V., Soldatov E.O., Yufereva V.A. Sistema kodov dlya fizicheskogo proektirovaniya reaktora na bystrykh neytronakh so svintsovym teplonositelem [System of codes for physical design of the lead-cooled fast reactor]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2020, no. 3, pp. 30–38.
- MCU-BR with MDBBR50 constant library. Certification passport of the software no 405 dated 08.12.2016.
- Gurevich M.I., Shkarovsky D.A. Raschet perenosa neytronov metodom Monte-Karlo po programme MCU. Uchebnoe posobie [Calculation of neutron transport by the Monte Carlo method using the MCU Program. Textbook]. Moscow, NIYaU MIFI Publ., 2012. 156 p.
- FACT-BR (version 1.1). Certification passport of the software no 433 dated 02.27.2018.
- Shibata K., Iwamoto O., Nakagawa T., Iwamoto N., Ichihara A., Kunieda S., Chiba S., Furutaka K., Otuka N., Ohsawa T., Murata T., Matsunobu H., Zukeran A., Kamada S. and Katakura J. JENDL-4.0: A New Library for Nuclear Science and Engineering. J. Nucl. Sci. Technol., 2011, vol. 48(1), pp. 1–30.
- MacFarlane R.E., Kahler A.C. Methods for Processing ENDF/B-VII with NJOY. LANL, 2010.
- Zabrodskaya S.V., Ignatyuk A.V., Koshecheev V.N., Manochin V.N., Nikolaev M.N., Pronyaev V.G. ROSFOND – Rossiyskaya natsional''naya biblioteka otsenennykh neytronnykh dannykh [RUSFOND – Russian national library of evaluated neutron data]. Voprosy atomnoy nauki i tekhniki. Ceriya: Yadernye konstanty – Problems of Atomic Science and Technology. Series: Nuclear Constants, 2007, no. 1–2, pp. 3–21.
- Golovko Yu.E., Koscheev V.N., Lomakov G.B., Manturov G.N., Rozhikhin E.V., Semenov M.Yu., Tsiboulya A.M., Yakunin A.A. Verifikatsiya sovremennoy versii konstant BNAB i programmy podgotovki CONSYST v raschetakh kritichnosti [Verifcation of ABBN constants and CONSYST code in criticality calculations]. Izvestiya vuzov. Yadernaya Energetika. 2014, no. 2, pp. 99–108. DOI: https://doi.org/
10.26583/npe.2014.2.11.
- Borovskaya Zh.V., Zhirnov A.P., Kalugina K.M., Moiseev A.V., Rozhdestvenskii I.M., Yufereva V.A. Verification of the MCU-BR software system based on the results of critical experiments using the
BFS-2 facility. At Energy, 2021, no. 130, issue 5, pp. 255–261. DOI: https://doi.org/10.1007/s10512-021-00805-9.
- Bednyakov S.M., Bezborodov A.A., Doolin V.A. Eksperimental''nye issledovaniya neytronno-fizicheskikh kharakteristik modeli aktivnoy zony reaktora BREST-OD-300 na stende BFS-2 [Experimental studies of the neutron-physical characteristics of the BREST-OD-300 reactor core model on BFS-2 stand]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornye konstanty – Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2024, no. 4, pp. 29–36.
- BN-600 Hybrid Core Benchmark Analyses. IAEA-TECDOC-1623. Venna: IAEA, Feb. 2010.
- Momotov V.N., Erin E.A., Volkov A.Yu. et al. Radiokhimicheskiy i elementarnyy analiz smeshannogo uran-plutonievogo topliva, obluchennogo v reaktore BN-600 [Radiochemical and elemental analysis of mixed uranium-plutonium nitride fuel irradiated in the BN-600 reactor]. Radiokhimiya – Radiochemistry, 2022, vol. 64, no. 1, pp. 53–59.
- Janis 4.0. User’s Guide. Revision 1, Oct. 2013.
- Soldatov E.O., Zhirnov A.P., Moiseev A.V. et al. Modelirovanie kampanii bystrogo reaktora so svintsovym teplonositelem na ves' srok ekspluatatsii [Simulation of lead-cooled fast reactor campaign for the entire service life]. Sbornik dokladov VI Mezhdunarodnoy nauchno-tekhnicheskoy konferentsii “Innovatsionnye proekty i tekhnologii yadernoy energetiki” [Proc. of the VI International Scientific and Technical Conference “Innovative Designs and Technologies of Nuclear Power”]. Moscow, November 14–17, 2023. Moscow, NIKIET Publ., 2023. Pp. 5–13.
UDC 621.039.51
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2026, no. 1, 1:7
