MOX-fuel

Experimental Justification of the Operability and Safety of Nuclear Fuel in the MIR.M1 Reactor

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

Tuzov A.A. Izhutov A.L. Petelin A.L. Burukin A.V. Ovchinnikov V.A. Dreganov O.I. Eshcherkin A.G. Kiseleva I.V. Kudrina I.V. Kudrin Yu.S. Alekseev A.V. Kuznetsova E.E. Mokeichev M.A. Markelov A.N. Sychugov M.S. Ziyatdinov E.Zh. Yashin R.A.

Computational Studies of Reactivity Effects in Severe Accidents, Accounting for Sodium Boiling, Fuel Cladding Melting, and Fuel Melting in a High-Power Sodium-Cooled Fast Reactor

5/18/2026 2026 - #02 Modelling Processes at Nuclear Facilities

Averchenkova E.P. Peregudov A.A. Solomonova N.V. Schekotova L.A. Khomyakov Yu.S. Chernukhina Yu.V. Volkov A.V. Shvetsov Yu. E.

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.

Computational Analysis of Burnup and Actinides Accumulation in a Reactor with a Controlled Neutron Spectrum

6/05/2024 2024 - #02 Modelling processes at nuclear facilities

Egorov G.O. Levchenko Y.V. Manturov G.N. Matveev Y.V.

Computational Analysis of the Closed Fuel Cycle of a VVER-1200 Reactor Based on Plutonium From Spent Nuclear Fuel

6/05/2024 2024 - #02 Modelling processes at nuclear facilities

Isanov K.A. Kolesov V.V. Korobeynikov V.V. Usanov V.I. Khnykina E.S.

Some Economic Aspects of Reducing Americium Production in a Two-Component System of Thermal and Fast Reactors

9/25/2023 2023 - #03 Fuel cycle and nuclear waste management

Gulevich A.V. Usanov V.I. Dekusar V.M. Eliseev V.A. Moseev A.L. Khnykina E.S.

Multi-criteria analysis of the efficiency of the scenarios for the development of nuclear power engineering in Russia under conditions of uncertainty of knowledge about the future

9/16/2020 2020 - #03 Current issues in nuclear energy

Zrodnikov A.V. Moseev A.L. Egorov A.F. Dekusar V.M.

Verification of the ROSFOND/ABBN nuclear data based on the OECD/NEA benchmark on criticality safety of MOX-fueled systems

9/20/2018 2018 - #03 Global safety, reliability and diagnostics of nuclear power installations

Andrianova O.N. Golovko Yu. E. Manturov G.N.

On feasibility of using nitride and metallic fuel in the MBIR reactor core

3/28/2016 2016 - #02 Physics and technology of nuclear reactors

Eliseev V.A. Korobeinikova L.V. Maslov P.A. Malysheva I.V. Matveev V.I. Demeneva I.V.

Prospects of VVER-SKD in a closed fuel cycle

4/04/2015 2015 - #01 Current issues in nuclear energy

Glebov A.P. Klushin A.V. Baranayev Yu.D.