Izvestiya vuzov. Yadernaya Energetika

The peer-reviewed scientific and technology journal. ISSN: 0204-3327

Operating Experience and Service Life Extension of the BOR-60 Experimental Fast Reactor

5/18/2026 2026 - #02 Safety, Reliability and Diagnostics of NPI

Tuzov A.A. Izhutov A.L. Krasheninnikov Yu.M. Zhemkov I.Yu. Petelin A.L. Naboyshchikov Yu.V. Neustroev V.S. Kireev N.V. Popyvanov K.V.

DOI: https://doi.org/10.26583/npe.2026.2.07

UDC: 621.039.51

The fast-neutron sodium-cooled reactor BOR-60 has been in operation since late 1969, running at design parameters for over 55 years. The reactor was designed as a prototype for a fast-neutron nuclear power plant, aiming to validate fundamental design engineering solutions for advanced fast power reactors. The originally planned 20-year service life has been extended several times, based on positive performance results of the equipment and systems, as well as on assessments of residual life – using refined data on the radiation and corrosion resistance of core components, equipment, and sodium circuit piping. The reactor plant has been operated without replacing the main process equipment of the first and second sodium-coolant cooling circuits, as well as the key components of the third steam-water circuit – such as the steam turbine, electric generator, etc. The operational experience gained from the BOR-60 reactor was used in the development of the BN-350 and BN-600 power reactors, as well as in new-generation BN reactor projects. Large-scale high-dose testing of various fuel and structural materials for different types of nuclear and thermonuclear reactors has been conducted and is still ongoing in the BOR-60 reactor. Research has been carried out on the physics, dynamics, and safety of BN-type reactors, along with the verification of computational codes, etc. The paper presents the main operational results, including work on the computational and experimental justification for extending the service life of the BOR-60.

References

  1. Tuzov A.A., Izhutov A.L., Krasheninnikov Yu.M., Zhemkov I.Yu., Kryukov F.N. Role of the BOR-60 research reactor in the development of fast reactors. Atomic Energy. 2024;136(5–6):233–244. DOI: https://doi.org/10.1007/s10512-024-01156-x
  2. Gadzhiev G.I., Efimov V.N., Zhemkov I.Yu., Korol’kov A.S., Polyakov V.I., Shtynda Yu.E., Revyakin Yu.L. Some Experimental Work Performed at the BOR-60 Reactor. Atomic Energy. 2001;91(5):913–922. DOI: https://doi.org/10.1023/A:1014265807449
  3. Momotov V.N., Volkov A.Yu., Tikhonova D.E. Post-irradiation radiochemical studies of neptunium and americium dioxides irradiated in the BOR-60 reactor. Scientific Annual Report of RIAR JSC – 2023. Dimitrovgrad, 2024, RIAR JSC Publ., p. 193–196. URL: https://elibrary.ru/download/elibrary_60033444_20958535.pdf (accessed Apr. 10, 2026) (in Russian).
  4. Izhutov A.L., Krasheninnikov Y.M., Zhemkov I.Y., Varivtsev A.V., Naboishchikov Y.V., Neustroev V.S., Shamardin V.K. Prolongation of the BOR-60 reactor operation. Nuclear Engineering and Technology. 2015;47(3):253–259. DOI: 10.1016/j.net.2015.03.002
  5. Izhutov A.L., Petelin A.L., Krasheninnikov Yu.M., Zhemkov I.Yu., Kharlov V.B. Experience in operating the BOR-60 reactor facility: work on improving safety and extending the service life. In proc. International Conference “Safety of Research Nuclear Installations”: Abstracts. Dimitrovgrad, 2021, p. 7–8. URL: https://www.niiar.ru/publishing/conference-proceedings (accessed Apr. 10, 2026) (in Russian).
  6. Mosunova N.A. The EVKLID/V1 integral code for safety justification of fast neutron reactor plants with liquid metal coolant. Part 1: Basic models. Thermal Engineering. 2018;5:69–84. DOI: https://doi.org/10.1134/S0040363618050065 (in Russian).
  7. Veprev D.P., Kuzmichev S.A., Shershov A.V., Mosunova N.A., Strizhov V.F., Boev A.V., Zhemkov I.Yu., Naboischikov Yu.V. Validation of the EVKLID/V1 integral calculation code using BOR-60 experimental data. Atomic Energy. 2023;134(3–4):177–181. DOI: 10.1007/s10512-024-01047-1
  8. Izhutov A.L., Krasheninnikov Yu.M., Poloz M.V., Boltyrov A.A., Nikitchenko I.A. Computational justification of the strength of critical components of the BOR-60 reactor facility during service life extension. Proc. of the 24th International Conference of Young Specialists on Nuclear Power Plants. OKB “Gydropress”, Podolsk, 2024, p. 90–98 (in Russian).
  9. Zhemkov I.Yu. Scientific and Methodological Support for the Operation of a Fast Neutron Research Reactor: Abstract of the Doctoral Thesis (Engineering). Dimitrovgrad, 2014. URL: https://www.dissercat.com/content/nauchno-metodicheskoe-soprovozhdenie-ekspluatatsii-issledovatelskogo-reaktora-na-bystrykh-ne (accessed Apr. 10, 2026) (in Russian).
  10. Zhemkov I.Yu., Naboischikov Yu.V., Ishunina O.V., Popyvanov K.V. Computational and experimental assessment of neutron fluence and damage dose on critical components of the BOR-60 reactor. Scientific Annual Report of RIAR JSC – 2023. Dimitrovgrad, 2024, RIAR JSC Publ., p. 53–55. URL: https://elibrary.ru/download/elibrary_60033257_57997567.pdf (accessed Apr. 10, 2026) (in Russian).
  11. Merkulov A.I., Zhemkov I.Yu., Naboischikov Yu.V., Popyvanov K.V. Calculation of neutron fluence and damage dose on critical components of the BOR-60 reactor using an improved neutron-physical model with the next-generation MCU-FR code. Scientific Annual Report of RIAR JSC – 2024. Dimitrovgrad, 2025, RIAR JSC Publ., p. 43–45. URL: https://elibrary.ru/download/elibrary_82507811_67999246.pdf (accessed Apr. 10, 2026) (in Russian).
  12. Izhutov A.L., Krasheninnikov Yu.M., Poloz M.V., Boltyrov A.A., Nikitchenko I.A. Computational aspects of extending the service life of the BOR-60 reactor facility. 12th Inter-Industry Seminar “Strength and Reliability of Equipment”. JSC “NIKIET”. Zvenigorod, 2024, p. 75–81 (in Russian).
  13. Rules for Strength Calculation of Equipment and Piping of Nuclear Power Installations (PNAE G-7-002-86). Moscow, Energoatomizdat Publ., 1989. URL: https://docs.cntd.ru/document/1200037730 (accessed Apr. 10, 2026) (in Russian).
  14. Kryukov F.N., Belyaeva A.V., Nikitin O.N., Grin P.I., Zhemkov I.Yu., Skupov M.V., Tarasov B.A., Zabudko L.M. Results of irradiation in BOR-60 and post-irradiation studies of experimental fuel rods with mixed nitride uranium-plutonium fuel. Atomic Energy. 2024;136(5–6):208–212. URL: https://j-atomicenergy.ru/index.php/ae/article/view/5397/5388 (accessed Apr. 10, 2026) (in Russian).
  15. Zhemkov I.Yu., Naboischikov Yu.V. Efficiency of minor actinide burning in fast and intermediate neutron spectra. Problems of Atomic Science and Technology. Series: Nuclear Reactor Constants. 2025;1:31–43. URL: https://vant.ippe.ru/images/pdf/2025/issue2025-1-31-43.pdf (accessed Apr. 10, 2026). EDN: EIBJPR (in Russian).

BOR-60 reactor plant nuclear core fuel element assembly operational life extension material resistance CRS

Link for citing the article: Tuzov A.A., Izhutov A.L., Krasheninnikov Yu.M., Zhemkov I.Yu., Petelin A.L., Naboyshchikov Yu.V., Neustroev V.S., Kireev N.V., Popyvanov K.V. Operating Experience and Service Life Extension of the BOR-60 Experimental Fast Reactor. Izvestiya vuzov. Yadernaya Energetika. 2026, no. 2, pp. 97-114; DOI: https://doi.org/10.26583/npe.2026.2.07 (in Russian).

Open PDF file