Minimizing Reactivity Margin of BN-1200 Reactor: Feasibility and Expediency
9/17/2026 2026 - #03 Current issues in nuclear energy
Vasilyev B.A. Bogdanova E.V. Kiselev A.V.
https://doi.org/10.26583/npe.2026.3.01
UDC: 621.039.51
The problem of minimizing the reactivity margin of a large fast reactor (BN-1200 type) is discussed. It is noted that minimizing the reactivity margin essentially boils down to minimizing the loss of reactivity during fuel burnup. Technical solutions are presented that provided a decrease in the reactivity margin during fuel burnup in the BN-1200 reactor design compared to this parameter in BN-600 and BN-800 reactors. In addition, methods are considered to reduce the loss of reactivity during fuel burnup and minimize the reactivity margin. It is estimated that, given the uncertainties in assessing the reactivity margin in BN-600 and BN-800 reactors, the minimum reactivity margin for fuel burnup in a BN-1200 reactor can be about 0.3% Δk/k, and the minimum reactivity margin that must be taken into account in reactor safety analyses should be taken at 0.5% Δk/k. An analysis of the effectiveness for achieving the minimum possible reactivity margin was performed, which showed a relatively small significance of the possible in practice minimization of the reactivity margin for the reactor safety indicators and a large significance of the economic minimization in the event of a significant initial reactivity margin.
References
- Vasiliev B.A., Belov S.B., Kiselev A.V., Eliseev V.A., Khomiakov Iu.S., Rodina E.A. Unification of the BN-1200 reactor core designs with MOX and MNUP fuel. Nuclear Engineering and Design. 2021;382:111387. DOI: https://DOI.org/10.1016/j.nucengdes.2011.111387
- Vasiliev B.A., Farakshin M.R., Belov S.B., Kiselev A.V., Klinov D.A., Gulevich A.V., Eliseev V.A., Malyshev I.V. Specific features of BN-1200 core in case of use of nitride or MOX fuel. International Conference on ‘‘Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development’’, Yekaterinburg, Russian Federation, 26–29 June 2017, IAEA-CN245-408.
- Belov S.B., Vasiliev B.A., Kuznetsov A.E., Farakshin M.R. Realization of BN-800 objectives in working out the elements of CNFC. Atomic Energy. 2025;138(1-2):31–37. URL: https://j-atomicenergy.ru/index.php/ae/article/view/5467 (accessed Aug. 10, 2026) (in Russian).
- Kuznetsov A.E., Vasiliev B.A., Farakshin M.R., Belov S.B., Sheryakov V.S. The BN-800 core with MOX fuel. International Conference on ‘‘Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development’’, Yekaterinburg, Russian Federation, 26–29 June 2017, IAEA-CN245-405.
- Yaroslavtseva L.N. A set of JAR programs for calculating the neutron-physical characteristics of nuclear reactors. Problems of atomic science and technology. Series: Physics and Technology of Nuclear Reactors. 1983;8(37):41–43 (in Russian).
- Rodina E.A., Egorov A.V., Rachkov V.I., Khomyakov Y.S. Modeling and comparative analysis of the transition to the equilibrium mode of the core BN-1200 with a homogeneous and heterogeneous layout. Collection of reports of the industry scientific and technical conference “Closing the fuel cycle of nuclear energy based on fast neutron reactors,” Sochi, October 28–29, 2021, p. 124–136 (in Russian).
- Vasiliev B.A., Farakshin M.R., Belov S.B., Radionycheva A.A., Kiselev A.V., Kuznetsov A.E. Increasing the efficiency of fuel use in BN reactors by introducing an axial reproducing layer into the core. Scientific and technical conference of JSC ‘‘TVEL’’ ‘‘New generation nuclear fuel for nuclear power plants. Development results, operating experience and directions of development’’ (NTK-2016). Moscow, VNIINM, November 16–17, 2016 (in Russian).
- Poplavsky V.M., Matveev V.I., Eliseev V.A., Kuznetsov I.A., Volkov A.V., Shvetsov Y.E., Khomyakov Y.S., Tsiboulia A.M. Studies on Influence of Sodium Void Reactivity Effect on the Concept of the Core and Safety of Advanced Fast Reactor. Journal of Nuclear Science and Technology. 2011;48(4):538–546. DOI: https://doi.org/10.1080/18811248.2011.9711731
- Vasiliev B.A., Kuzavkov N.G., Mishin O.V., Radionycheva A.A., Farakshin M.R., Bibilashvili Yu.K., Ivanov Yu.A., Medvedev A.V., Mitrofanova N.M., Tselishchev A.V., Zabudko L.M., Matveev V.I., Khomyakov Yu.S., Cherny V.A. Experience and perspectives of the BN-600 reactor core upgrade. Izvestiya vuzov. Yadernaya Energetika. 2011(1):158–168. EDN: OGKDUL. URL: https://static.nuclear-power-engineering.ru/journals/2011/01.pdf (accessed Aug. 10, 2026) (in Russian).
- Belov S.B., Vasilyev B.A., Farakshin M.R., Radionycheva A.A. Arrangement of the BN-600 reactor core refueling at transition to the increased fuel burnup. International Conference on ‘‘Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development’’, Yekaterinburg, Russian Federation, 26–29 June 2017, IAEA-CN245-386.
- Moiseev A.V., Semenov M.Yu., Khomyakov Yu.S., Zheltyshev V.A., Maltsev V.V., Roslyakov V.F., Belov A.A., Seleznev E.F., Vasiliev B.A., Farakshin M.R. Experimental and computational justification of the reactivity balance and power distribution in the BN-600 core. Izvestiya vuzov. Yadernaya Energetika. 2011(1):130–144. EDN: OGKDTR. URL: https://static.nuclear-power-engineering.ru/journals/2011/01.pdf (accessed Aug. 10, 2026) (in Russian).
- Klinov D.A., Semenov M.Yu., Mikhailov G.M., Peregudov A.A., Mishin V.A., Solomonova N.V., Kryukov A.N., Farakshin M.R., Belov S.B., Kuznetsov A.E., Ignatiev V.N., Dubova G.Yu. Calculation and experimental analysis of BN-800 neutron-physical characteristics during the transition to mixed oxide fuel loading. Atomic energy. 2023;135(1–2):1–11. URL: https://www.j-atomicenergy.ru/index.php/ae/article/view/5314 (accessed Aug. 10, 2026) (in Russian).
- Kulabukhov Yu.S., Roslyakov V.F., Farakshin M.R., Matvienko I.P., Suvorov V.D., Tkachuk N.N. Experimental determination of relative thermal displacement of CPS elements at the BN-600 reactor. Problems of atomic science and technology. Series: Physics and Technology of Nuclear Reactors. 1990;1:47–51 (in Russian).
- Danilychev A.V., Elistratov D.G., Stogov V.Yu., Chernyi V.A., Belov S.B., Vasiliev B.A., Farakshin M.R., Voronov S.A. Computational error in calculating reactivity effects in fast reactors and its effect on the assessment of the consequences of the main types of accidents (analysis of the IAEA test model). Atomic energy. 2004;97(5):323–333. URL: https://j-atomicenergy.ru/index.php/ae/article/view/3388 (accessed Aug. 10, 2026) (in Russian).
- Seleznev E.F. Kinetics of fast reactors. Moscow, Nauka Publ., 2004, pp. 82–116 (in Russian).
- Lukyanov D.A., Kudryaev A.A. Analysis of power fluctuations and reactivity of BN-800, according to reactor plant diagnostic system (RDS) readings. Problems of atomic science and technology. Series: Nuclear and reactor constants. 2024;4:87–97. EDN: LGAUJA. URL: https://vant.ippe.ru/images/pdf/2024/issue2024-4-87-97.pdf (accessed Aug. 10, 2026) (in Russian).
- Bolnov V.A., Bogdanova E.V., Malkin S.A. Buran program validation based on experiments. Problems of atomic science and technology. Series: Nuclear and Reactor Constants. 2022;4:176–184. EDN: AJVFGA. URL: https://vant.ippe.ru/images/pdf/2022/issue2022-4-176-184.pdf (accessed Aug. 10, 2026) (in Russian).
- Adamov E.O., Ashurko Yu.M., Egorov A.V., Khomyakov Yu.S., Muratov A.G., Orlov M.A., Orlov V.V., Rachkov V.I., Shvetsov Yu.E., Suslov I.R., Volkov A.V. Minimisation of Reactivity Margin for Equilibrium Core of Liquid Metal Cooled Fast Reactors. International Conference on ‘‘Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development’’, Yekaterinburg, Russian Federation, 26–29 June 2017, IAEA-CN245-131.
BN reactor MOX fuel MNUP fuel breeding ration of the core reactivity margin fuel burnup minimization of reactivity loss safety efficiency
Link for citing the article: Vasilyev B.A., Bogdanova E.V., Kiselev A.V. Minimizing Reactivity Margin of BN-1200 Reactor: Feasibility and Expediency. Izvestiya vuzov. Yadernaya Energetika. 2026, no. 3, pp. 7-26; DOI: https://doi.org/10.26583/npe.2026.3.01 (in Russian).
