01. Constant Support for Calculations of Thermal Neutron Reactors of the VVER Type

3/27/2026 2026 - #01 Current issues in nuclear energy

Kalugin M.A. Lazarenko A.P. Lizorkin M.P. Semchenkov Yu.M. Shkarovsky D.A.

02. Verification of the BNAB‑RF22 Constant Library for Neutronic Calculations of BN‑600 and BN‑800 Reactors

3/27/2026 2026 - #01 Current issues in nuclear energy

Panova D.V. Peregudov A.A. Manturov G.N. Semenov M.Yu. Mishin V.A.

03. Development and Testing of a High-Temperature Treatment Facility Mock-Up for Pyroprocessing of Mixed Uranium-Plutonium Nitride SNF at Reprocessing Module of Experimental and Demonstration Energy Complex

3/27/2026 2026 - #01 Physics and technology of nuclear reactors

Smirnov V.P. Samsonov A.A. Leshchenko A.Yu. Nosov A.V. Mochalov Yu.S. Savchits S.M. Legen’kij A.A.

04. Logistic Approximation of the Calibration Characteristics

3/27/2026 2026 - #01 Physics and technology of nuclear reactors

Yuferov A.G.

05. Hydrodynamics of Turbulent Coolant Flow at the Outlet of the Fuel Assembly of the RITM Reactor of a Low-Power Nuclear Power Plant

3/27/2026 2026 - #01 Thermal physics and thermal hydraulics

Dmitriev S.M. Demkina T.D. Dobrov A.A. Doronkov D.V. Pronin A.N. Ryazanov A.V. Karpuhov O.O. Samoilov O.B. Shipov D.L.

06. Technical Aspects of the Application of the Darcy Porous Body Model for the Preliminary Evaluation of Circuit Solutions in Nuclear Power Plants

3/27/2026 2026 - #01 Thermal physics and thermal hydraulics

Yaurov S.V. Povarov V.P. Chusov I.A.

07. Using the Operator’s Information Support System to Eliminate Excessive Activation of Safety Systems in Transients at VVER-1200 Power Units

3/27/2026 2026 - #01 Global safety, reliability and diagnostics of nuclear power installations

Tuchkov M.Yu. Povarov P.V. Mysin K.S.

08. Results of Operability Validation of BN-600 Reactor Permanent Components for Service Life Extension up to 60 Years

3/27/2026 2026 - #01 Nuclear materials

Vilensky O.Yu. Osetrov D.L. Pristrom S.A. Rogozhkin S.A. Staroverov A.I.

09. Neutron Thermal Scattering Models’ Impact on RBMK Dewatering Effect Calculations

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

Andrianova O.N. Ivanov I.E. Varfolomeeva V.A. Druzhinin V.E.

10. Results of Model Testing for Calculating Neutron-Physical Characteristics of the RBT-10/2 Reactor Core Based on Operational Data

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

Efimov E.I. Pimenov V.V. Malkov A.P.

11. 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.

12. Methodology for Developing Benchmarks for Neutronic Calculations of Generation IV Reactor Characteristics

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

Tikhomirov G.V. Ternovykh M.Y. Ryzhkov A.A. Gerasimov A.S.

13. Analysis of the Effectiveness of Fuel Composition Changing in a Pulse Fast-Neutron Research Reactor

3/27/2026 2026 - #01 Application of nuclear tech

Chereshkov D.G.

14. Two-Component Nuclear Power as a Tool for Solving Modern Problems in Conditions of Incomplete Knowledge about the Future Power Industry

3/27/2026 2026 - #01 Personnel training

Kuchinov V.P. Gorin N.V. Kuznetsov E.V. Korobeynikov V.V. Dekusar V.M. Shcheklein S.E.