EDN: BPBNXO
Authors & Affiliations
Kolesov V.V.1, Korobeynikov V.V.2, Gurskaya O.S.2, Pupko L.P.2
1 Obninsk Institute for Nuclear Power Engineering of the National Research Nuclear University, Obninsk, Russia
2 A.I. Leypunsky Institute for Physics and Power Engineering, Obninsk, Russia
Kolesov V.V.1 – Associate Professor, Dr. Sci. (Phys.-Math.).
Korobeinikov V.V.2 – Chief Researcher, Professor, Dr. Sci. (Phys.-Math.). Contacts: 1, pl. Bondarenko, Obninsk, Kaluga region, Russia, 249033. Tel.: +7 (484) 399-70-00(80-56); e-mail: This email address is being protected from spambots. You need JavaScript enabled to view it..
Gurskaya О.S.2 – Research Fellow.
Pupko L.P.2 – Research Fellow.
Abstract
Traditionally, it is assumed that fast neutron reactors should not contain substances that slow down neutrons, since deceleration reduces the reproduction coefficient, the large value of which is the main physical advantage of a fast reactor over other types of reactors. The material of fast neutron reactor reflectors is heavy 238U or 232Th, which at the same time are raw materials for the reproduction of new fissile materials. Such reflectors, of course, reduce the critical size of the active zones, but their main function is to accumulate new fissile materials resulting from the absorption of neutrons scattered by the core. Therefore, they are not called neutron reflectors, but reproduction zones. Nevertheless, the presence of a reproduction zone in a nuclear reactor is not always a necessary element. For example, the task may be to reduce the loading of fissile materials into the core of a fast neutron reactor, lengthen the fuel campaign and regulate it.
In this paper, the selection and comparison of the efficiency of reflectors made of different materials for low-power fast neutron reactors and small core sizes are investigated. The influence of reflectors on the duration of operation of such a reactor and the possibility of controlling it is considered.
Keywords
neutron reflectors, fast neutron reactors, duration of the nuclear reactor campaign, efficiency of reflectors made of different materials
Article Text (PDF, in Russian)
References
- McClure P.R. et al. Design of Megawatt Power Level Heat Pipe Reactors. RepLA-UR-15-28840, Los Alamos National Laboratory, Nov. 2015.
- Jaakko Leppanen. PSG2/SERPENT – A Continious Energy Monte-Carlo Reactor Physics Burnup Calculation Code, Helsinki: VTT Technical Research Centre of Finland, 2015. Available at: https://serpent.vtt.fi/download/Serpent_manual.pdf (accessed 17.01.2025).
- Japan Atomic Energy Agency – Nuclear Data Center. Japanese standard library for fast breeder reactors, thermal reactors, fusion neutronics and shielding calculations, and other applications (JENDL-4.0). JAEA-NDC, 2010. Available at: https://wwwndc.jaea.go.jp/jendl/j40/j40.html (accessed 17.01.2025).
- Kolesov V.V., Korobeynikov V.V., Mikhalev A.V., Pupko L.P. Vliyaniye spektral'nykh i geterogennykh effektov na effektivnost' vyzhiganiya minornykh aktinidov [Impact of spectral and heterogeneous effects on the minor actinides burning efficiency]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology.Series: Nuclear and Reactor Constants, 2023, issue 1, pp. 74–90.
- Golbuev V.I., Zvonarev A.V., Nikolaev M.N. et al. The effect of reflectors made of different materials on the increase in the number of neutron captures in uranium blanket of a fast-neutron reactor. At Energy, 1963, vol. 15, issue 3, pp. 966–967. DOI: https://doi.org/10.1007/BF01118349.
- Kulikov G.G., Shmelev A.N., Apse V.A., Kulikov E.G. Svinets, soderzhashchiy izotop Pb-208, – tyazhelyy zamedlitel' i otrazhatel' neytronov. Yego neytronno-fizicheskiye svoystva [Lead containing the isotope Pb-208 – a heavy moderator and reflector of neutrons. Its neutron-physical properties]. Nauchnaya sessiya MIFI-2011 [Scientific session MEPhI-2011]. MEPhI, 2011, vol. 1 – Innovative nuclear technologies, p. 49.
- L’vova E.M., Chebeskov A.N. Analiz privlekatel'nosti materialov primenitel'no k toplivnomu tsiklu bystrogo reaktora tipa BN bol'shoy moshchnosti [Analyses of the attractiveness of materials as applied to the fuel cycle of large capacity fast reactor of BN-type]. Izvestiya vuzov. Yadernaya Energetika, 2016, no. 2, pp. 35–44. DOI: https://doi.org/10.26583/npe.2016.2.04.
- Kochnov O.Yu., Kolesov V.V. Otrazhatel' neytronov yadernogo reaktora tipa VVR [Neutron reflector for a nuclear reactor of the VVR type]. Patent for utility model No. 168758, 2017.
- Sinyavsky V.V. Obzor rezul'tatov eksperimental'nykh issledovaniy neytronno-fizicheskikh kharakteristik termoemissionnykh reaktorov-preobrazovateley na bystrykh neytronakh [Review of the results of experimental studies of the neutron-physical characteristics of thermionic reactors-converters on fast neutrons]. Available at: https://cyberleninka.ru/article/n/obzor-rezultatov-eksperimentalnyh-issledovaniy-neytronno-fizicheskih-harakteristik-termoemissionnyh-reaktorov-preobrazovateley-na (accessed 21.01.2025).
- Isakov A.I., Kazarnovskiy M.V., Medvedev Yu.A., Metelkin Ye.V. Nestatsionarnoye zamedleniye neytronov (osnovnyye zakonomernosti i nekotoryye prilozheniya). Monografiya [Non-stationary slowing down of neutrons (basic regularities and some applications). Monograph]. Moscow: Nauka Publ., 1984. 264 p.
- Shmelev A.N., Apse V.A., Kulikov G.G., Kulikov E.G. Mnogosloynyye otrazhateli neytronov [Multilayer Neutron Reflectors]. Izvestiya vuzov. Yadernaya Energetika, 2024, no. 4, pp. 34–46. DOI: https://doi.org/10.26583/npe.2024.4.03 (in Russian).
- Bell G.I., Glasstone S. Nuclear Reactor Theory. New York, Van Nostrand Reinhold Ltd., 1970. 619 p.
- Shmelev A.N., Kulikov G.G., Kryuchkov E.F., Apse V.A., Kulikov E.G. Application of Radiogenic Lead with Dominant Content of 208Pb for Long Prompt Neutron Lifetime in Fast Reactor. Nuclear Technology, 2013, vol. 183, no. 3, pp. 409–426.
- Manturov G.N., Zabrodskaya S.V., Zuikov A.A., Levchenko Yu.V., Melega N.A., Mishin V.A., Panova D.V., Peregudov A.A., Peregudova O.O., Semenov M.Yu., Slyunyaev M.N., Tykleeva K.V. Sostoyaniye razrabotki baz dannykh yadernykh konstant dlya raschetov bystrykh reaktorov na osnove ROSFOND i BNAB-RF [Status of development of nuclear constant databases for calculations of fast reactors based on ROSFOND and BNAB-RF libraries]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology.Series: Nuclear and Reactor Constants, 2022, issue 3, pp. 19–26. Available at: https://vant.ippe.ru/images/pdf/2022/issue2022-3-19-26.pdf (accessed 21.01.2025).
- Peregudov A.A., Kryachko M.V., Koshcheyev V.N., Maslov P.A., Tormyshev I.V., Semenov M.Yu., Kunts'o G.A., Gurskaya O.S., Ivanov A.A., Yerpalov P.A. BNcode – usovershenstvovannyy kod dlya nauchnogo soprovozhdeniya deystvuyushchikh reaktorov BN [BNcode – improved code for scientific support of existing BN reactors]. Voprosy atomnoy nauki i tekhniki. Seriya: Yaderno-reaktornyye konstanty – Problems of Atomic Science and Technology.Series: Nuclear and Reactor Constants, 2019, issue 2, pp. 77–86.
UDC 621.039.54(04)
Problems of Atomic Science and Technology. Series: Nuclear and Reactor Constants, 2025, no. 1, 1:5