Izvestiya vuzov. Yadernaya Energetika

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

Research of the Possibility of Increasing Plutonium Production in Fast Reactors by Using Graphite in Breeding Zones

3/27/2026 2026 - #01 Modelling processes at nuclear facilities

Kolesov V.V. Korobeynikov V.V. Terekhova A.M.

DOI: https://doi.org/10.26583/npe.2026.1.11

UDC: 621.039.59

The article studies the possibility of increasing plutonium production in fast reactors by using graphite in breeding zones. The problem of resource provision of nuclear power through the development of a closed fuel cycle is considered, where the key role is played by the breeding of plutonium as a secondary fuel. The main idea of the work is that softening the neutron spectrum in the breeding zones using graphite increases the capture of neutrons by U-238 nuclei, which increases the production of plutonium. To test this idea, calculations were performed using the SERPENT software package on a model of the BN reactor (Heat capacity of 550 MW). Two options for the placement of graphite were studied: axial arrangement (graphite along the boundaries of the breeding zone and in its center) and radial arrangement (graphite in the side zones). The results showed that the use of graphite increases the production of plutonium. A change in the isotopic composition of plutonium was also revealed: in systems with graphite, the proportion of Pu-241 increases, and Pu-239 decreases, which is important for the fuel cycle. The calculations showed that graphite in the breeding zones effectively softens the neutron spectrum, increasing the capture of neutrons by U-238; the greatest increase in plutonium production (up to 22%) is achieved with central placement of graphite in axial zones; the results confirm the prospects of using graphite in BN reactors for optimizing the closed NFC.

References

  1. Bobrov S.B., Danilychev A.V., Eliseev V.A., Zhukova O.A., Zverkov Yu.A., Ilyunin V.G., Matveev V.P., Morozov A.G., Murogov V.M., Novozhilov A.I., Orlov V.V., Slesarev I.S., Subbotin S.A., Troyanov M.F., Shafrygin B.F. Paths for the development of fast power reactors with a high breeding factor. Atomic Energy. 1983;54(4):279–284. DOI: https://doi.org/10.1007/BF01123810
  2. Bobrov S.B., Kazachkovsky O.D., Matveev V.I., Troyanov M.F. Fuel-cycle parameters for fast reactors with various core types. Atomic Energy. 1989;64(1):67–73. DOI: https://doi.org/10.1007/BF01124008
  3. Alekseev P.N., Balanin A.L., Dekusar V.M., Egorov A.F., Klinov D.A., Korobeynikov V.V., Ma-rova E.V., Maslov A.M., Nevinitsa V.A., Staroverov A.I., Fomichenko P.A., Shepelev S.F., Shirokov A.V. Development of BN-1200 physical and technical design solutions aimed at improvement of SFR technology competitiveness. Problems of atomic science and technology. Series: Nuclear and reactor constants. 2018;2:71–83. URL: https://vant.ippe.ru/images/pdf/2018/2-8.pdf (accessed Mar 10, 2026) (in Russian).
  4. Alekseev P.N., Gagarinskii A.Yu., Kalugin M.A., Kukharkin N.E., Semchenkov Yu.M., Sidorenko V.A., Subbotin S.A., Teplov P.S., Fomichenko P.A., Asmolov V.G. On the strategy for the development of nuclear Power in Russia. Atomic Energy. 2019;126(4):207–212. DOI: https://doi.org/10.1007/s10512-019-00538-w
  5. Alekseev P.N., Alekseev S.V., Andrianova E.A., Asmolov V.G., Dekusar V.M., Zrodnikov A.V., Kagramanyan V.S., Koltun O.V., Pavlov A.S., Ponomarev Stepnoy N.N., Subbotin S.A., Temishev R.R., Teplov P.S., Usanov V.I., Tsibulsky V.F. Two-component nuclear energy system with thermal and fast reactors in a closed nuclear fuel cycle (ed. by N.N. Ponomarev-Stepnoy). Moscow, Tekhnosphere Publ., 2016, 160 p. URL: https://elib.biblioatom.ru/text/dvuhkomponentnaya-yadernaya-systema_2016 (accessed Mar.10, 2026) (in Russian).
  6. Petrov A.Yu., Shutikov А.V., Ponomarev-Stepnoy N.N., Bezzubtzev V.S., Bakanov M.V., Troyanov V.M. Prospects of creation of the dual component nuclear energy system. Izvestiya vuzov. Yadernaya Energetika. 2019;2:5–15. DOI: https://doi.org/10.26583/npe.2019.2.01 (in Russian).
  7. Soloveva A.P., Uliyanin Y.A., Kharitonov V.V., Yurshina D.Yu.The value of spent nuclear fuel as a raw material for fueling reactors on thermal neutrons. Izvestiya vuzov. Yadernaya Energetika. 2019;2:140–152. DOI: https://doi.org/10.26583/npe.2019.2.12 (in Russian).
  8. Alekseev P.N., Blandinskii V.Yu., Balanin A.L., Grol A.V., Nevinitsa V.A., Teplov P.S., Fomichenko P.A., Gulevich A.V., Dekusar V.M., Egorov A.F., Korobeinikov V.V., Moseev A.L., Marova E.V., Maslov A.M., Farakshin M.R., Shepelev S.F., Shirokov A.V. Efficiency Assessment of Nuclear Energy Development Scenarios for Russia Using Multi-Criteria Analysis. Atomic Energy. 2020;128(1):3–6. DOI: https://doi.org/10.1007/s10512-020-00641-3
  9. Egorov A.F., Klinov D.A., Korobeynikov V.V., Moseev A.L., Marova E.V., Shepelev S.F. Results of multi-criteria analysis of nuclear development scenarios in russia including total energy mix in the state. Problems of atomic science and technology. Series: Nuclear and reactor constants. 2017;4:64–79. URL: https://vant.ippe.ru/en/year2017/4/neutron-constants/1394-7.html (accessed Mar. 10, 2026) (in Russian).
  10. Kagramanyan V.S., Kalashnikov A.G., Kapranova E.N., Puzakov A.Yu. Comparison of fuel cycles characteristics for nuclear energy systems based on VVER-TOI and BN-1200 reactors. Izvestiya vuzov. Yadernaya Energetika. 2014;4:92–101. DOI: https://doi.org/10.26583/npe.2014.4.10 (in Russian).
  11. Dekusar V.M., Kagramanyan V.S., Kalashnikov A.G., Korobeynikov V.V., Korobitsyn V.E., Klinov D.A. Developing Mathematical Model for Nuclear Energy Fuel Cycle Based on Thermal and Fast Reactors. Izvestiya vuzov. Yadernaya Energetika. 2010;4:119–132. URL: https://nuclear-power-engineering.ru/full-issue/2010-04/ (accessed Mar 10, 2026) (in Russian).
  12. Kalashnikov A.G., Moseev A.L., Dekusar V.M., Korobeynikov V.V., Moseev P.A. Development of the code CYCLE for nuclear fuel cycle analysis. Izvestiya vuzov. Yadernaya Energetika. 2016;1:91–99. DOI: https://doi.org/10.26583/npe.2016.1.10 (in Russian).
  13. Seleznev E. Kinetics of fast neutron Reactors (Ed. by A.A. Sarkisov). Moscow, Nauka Publ., 2013, 237 p. URL: https://ibrae.ac.ru/docs/109/seleznev.pdf (accessed Mar 10, 2026) (in Russian).
  14. Bakanov M.V. Solution of scientific and technical problems of operation of «fast» reactors – from BN-600 to BN-800. Abstracts of the 9th international scientific and technical conference «Safety, efficiency and economy of nuclear power». Moscow, JSC Rosenergoatom Concern, 2014, p. 7–8 (in Russian).
  15. Leppanen J. Serpent – a Continious-energy Monte-Carlo Reactor Physics Burnup Calcula tion Code. Helsinki, VTT Technical Research Centre of Finland, 2015, 164 p. URL: https://serpent.vtt.fi/serpent/download/ (accessed Mar 10, 2026).

fast reactor graphite plutonium breeding zone

Link for citing the article: Kolesov V.V., Korobeynikov V.V., Terekhova A.M. Research of the Possibility of Increasing Plutonium Production in Fast Reactors by Using Graphite in Breeding Zones. Izvestiya vuzov. Yadernaya Energetika. 2026, no. 1, pp. 133-143; DOI: https://doi.org/10.26583/npe.2026.1.11 (in Russian).

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