Izvestiya vuzov. Yadernaya Energetika

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

Use of MOX Fuel in BN-800 Reactor

9/10/2025 2025 - #03 Current issues in nuclear energy

Vasilyev B.A. Kryukov A.N. Farakshin M.R. Belov S.B. Sheryakov V.S. Kuznetsov A.E. Filin I.A.

DOI: https://doi.org/10.26583/npe.2025.3.03

UDC: 621.039.05:621.039.526

In accordance with the strategy for the development of two-component nuclear energy with NFC closure adopted in the Russian Federation, fast neutron reactors must ensure the effective use of mixed uranium-plutonium fuel based on plutonium extracted from SNF of thermal reactors, and then from their own SNF. The first domestic BN reactors used fuel developed by that time based on enriched uranium dioxide. The development of mixed uranium-plutonium oxide (MOX) fuel began with the irradiation of experimental fuel assemblies (FAs) in the research reactor BOR-60, as well as power reactors BN-350 and BN 600. The BN-800 design was already focused on the use of mixed uranium-plutonium fuel.

Due to the delay in the launch of industrial production of MOX fuel created at the Mining and Chemical Combine, the BN-800 was launched (2016) with a hybrid core formed mainly from FAs with uranium fuel manufactured at MSZ JSC. The share of FAs with MOX fuel manufactured at the pilot production facilities of JSC SSC NIIAR and the Production Association MAYAK was 16%. The hybrid core was operated until the eighth operation cycle. The transition of BN-800 core to a full loading with MOX fuel was completed by the beginning of the 13th operation cycle (2023).

The period of transition to the core with a full loading with MOX fuel was characterized by a step-by-step increase, with an increase in the share of MOX FAs in the core, in the neutron flux density and, accordingly, the main operating parameters of fuel pins that determine their performance: linear thermal power, damaging dose to the cladding and fuel burnup.

For fabrication of MOX fuel, plutonium of different isotopic composition is used, which is ensured by the method implemented at the production site for adjusting the mass fraction of plutonium in the fuel. Currently, the core is being transferred to FAs with fuel cladding from more radiation-resistant steel EK164-CWAt that, which will subsequently allow starting work to increase fuel burnup. At that, compared with current core operation mode with the use of ChS68‑CW steel for pin cladding, it is planned to increase fuel burnup from 9.5% h.a. up to 12% h.a. by the maximum value and from 66 MW⋅d/kg to 86 MW⋅d/kg by the average value. As part of the development of the technology for burning out minor actinides from the 14thoperation cycle (2024), three FAs are irradiated in the reactor, which include four fuel elements each with the addition of americium (0.9%) and neptunium (0.6%).

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MOX fuel fast neutron reactor EFA BN-800 hybrid core plutonium isotopic composition minor actinides burnup

Link for citing the article: Vasilyev B.A., Kryukov A.N., Farakshin M.R., Belov S.B., Sheryakov V.S., Kuznetsov A.E., Filin I.A. Use of MOX Fuel in BN-800 Reactor. Izvestiya vuzov. Yadernaya Energetika. 2025, no. 3, pp. 45-59; DOI: https://doi.org/10.26583/npe.2025.3.03 (in Russian).

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