Journal Report

Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika

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Journal Information
Journal Title
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Publisher
Obninsk Institute for Nuclear Power Engineering, National Research Nuclear University 'MEPhI'
ISSN
0204-3327
E-ISSN
Database
SCOPUS
Domain
Physical Sciences, Social Sciences
Classification History
Year A+ A B C
2026 ✓
2025 ✓
2024 ✓
2023 ✓
2021/2022 ✓
2020 ✓
2019 ✓
2018
A journal may have more than one classification in the same year. All recorded classifications are displayed.
Recent Articles
Model of Cladding Axial Loading due to Friction of Nitride Fuel Pellets and Cladding in Fast Reactor
Vladimir I. Folomeev, Svetlana M. Ganina, Alexandr G. Isakov et al.
2026-9 Vol. 2026 Issue 3 Pages 207-219
DOI: 10.26583/npe.2026.3.15
Effects of Plasma Parameter Profiling on the Triple Product Criterion Determination for D-3He Tokamak Reactors
Veronika V. Verterovskaya, Aleksandr I. Godes, Vladimir L. Shablov
2026-9 Vol. 2026 Issue 3 Pages 168-181
DOI: 10.26583/npe.2026.3.12
Energy Distribution of Neutron Radiation Flux Density at Workplaces of the Rostov Nuclear Power Plant
Maria Dmitrievna Pyshkina, Maksim Evgenievich Vasyanovich, Konstantin Leonidovich Antonov et al.
2026-9 Vol. 2026 Issue 3 Pages 142-153
DOI: 10.26583/npe.2026.3.10
Proposals for the Development of the VVER-1200 and VVER-TOI Design Power Levels
Aleksey A. Dubov
2026-9 Vol. 2026 Issue 3 Pages 43-51
DOI: 10.26583/npe.2026.3.03
Development and Validation of Cold-Wall Correction for Correlations to Determine Critical Heat Flow in Fuel Assemblies of VVER Type Reactors
Daniil Evgenievich Ovsyannikov, Evgeny A. Vertikov, Dmitry A. Oleksyuk et al.
2026-9 Vol. 2026 Issue 3 Pages 95-110
DOI: 10.26583/npe.2026.3.07
Investigation of the Effect of Using a Radial Reflector on the Neutron-Physical Characteristics of the Small-Module Reactors
Alexandra A. Vorontsova, Ruslan Adhamovich Vnukov, Valeriy V. Kolesov
2026-9 Vol. 2026 Issue 3 Pages 182-195
DOI: 10.26583/npe.2026.3.13
Experience with Using the Coupled 1D-3D Thermal-Hydraulic Analysis to Simulate an Emergency Cooldown of a Sodium-Cooled Fast Reactor
Denis Vladimirovich Didenko, Artem Mikhailovich Anfimov, Oleg Leonidovich Nikanorov et al.
2026-9 Vol. 2026 Issue 3 Pages 62-79
DOI: 10.26583/npe.2026.3.05
Hydrodynamic Characteristics of Flow in a Fuel Rod Bundle of a Fuel Assembly for the RITM Reactor of a Low-Power Nuclear Power Plant
Sergey M. Dmitriev, Tatiana D. Demkina, Alexander A. Dobrov et al.
2026-9 Vol. 2026 Issue 3 Pages 80-94
DOI: 10.26583/npe.2026.3.06
Methodology for Determining Parameters of a Two-Phase Medium Using Computer Vision Tools
Nikita Valerievich Pavliukovski, Andrei Olegovich Tolokonski, Kirill Vladlenovich Kutsenko et al.
2026-9 Vol. 2026 Issue 3 Pages 111-122
DOI: 10.26583/npe.2026.3.08
Modeling of Multiple Fuel Recycling with Minor Actinides in High-Capacity Fast Power Reactors Using the Code System SCALE
Andrey Y. Khomyakov, Elena Aleksandrovna Rodina, Mikhail Yu. Ternovykh et al.
2026-9 Vol. 2026 Issue 3 Pages 220-232
DOI: 10.26583/npe.2026.3.16
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Printed: November 7, 2026 18:14