Title	Publication Date	Language	Citations
Use of Recovered Uranium and Plutonium in Thermal Reactors	2005/08/01	English	13
Hydrogen cycle based backup for NPP internal needs during a blackout	2013/08/01	English	13
On a nuclear power strategy of Russia to 2050	2012/02/01	English	12
IBR-2M Reactor Power Feedback Parameters Evaluation Using Square Reactivity Oscillations	2017/06/01	English	12
Current problems of probabilistic safety analysis of facilities using atomic energy	2008/02/01	English	12
Computational and Experimental Validation of a Passive Heat Removal System for NPP Containment with VVER-1200	2014/02/01	English	12
Corrosion Resistance and Mechanical Stability of Nickel Alloys in Molten-Salt Nuclear Reactors	2018/05/01	English	12
A Step in the Verification of the Hydra-Ibrae/LM/V1 Thermohydraulic Code for Calculating Sodium Coolant Flow in Fuel-Rod Assemblies	2015/10/01	English	12
Development and validation of a technology for removal of noncondensing gases to ensure the operability of a passive heat removal system	2006/01/01	English	12
Heat-and-Mass Transfer Intensification in Saturated-Steam Generators in NPP with VVER as a Means for Increasing Efficiency and Reliability	2018/01/01	English	12
The World’s First Floating NPP: Origination and Direction of Future Development	2020/11/01	English	12
Experimental Research on Thermophysical Processes for Safety Validation of new-Generation Vver	2014/07/27	English	12
Radiation resistance of high-density uranium—molybdenum dispersion fuel for nuclear research reactors	2006/01/01	English	11
Methods for calculating coupled reactor systems	2004/12/01	English	11
Use of the CFD-Code CONV-3D in Reactor Applications	2017/01/01	English	11
Next Generation Design Codes for a New Technological Platform for Nuclear Power	2016/09/30	English	11
LiF–NaF–KF Molten salt reactor with a fast neutron spectrum	2012/10/01	English	11
Topical Environmental Problems of Nuclear Power	2013/09/01	English	11
Combined vitrification of chloride and phosphate wastes by pyroelectrochemical reprocessing of nuclear fuel	2006/12/01	English	11
Measurement of Terbium Isotopes Yield in Irradiation of 151Eu Targets by 3He Nuclei	2017/11/01	English	11
Decontamination of radioactively contaminated soil at the Russian Science Center Kurchatov Institute	2007/12/01	English	11
Radiation damage in beryllium at 70–440°C and neutron fluence (0.3–18)·1022 cm−2 (E n > 0.1 MeV)	2006/10/01	English	11
Cascades with Flow Expansion for Simultaneous Concentration of Intermediate Components	2019/09/01	English	11
RITM-200: new-generation reactor for a new nuclear icebreaker	2013/04/01	English	10
Inclusion of Radioactive Ion-Exchange Resins in Inorganic Binders	2005/09/01	English	10
Purification of Regenerated Uranium Hexafluoride by Removal of 232,234,236U in the Intermediate Product of a Two-Feed-Flow Cascade	2019/06/01	English	10
Economic effect of the development and operation of serially produced propulsion nuclear power systems	2007/01/01	English	10
30 Years of experience in operating the BN-600 sodium-cooled fast reactor	2010/08/01	English	10
Two-Component Nuclear Power System with a Closed Nuclear Fuel Cycle Based on BN and VVER Reactors	2016/08/01	English	10
Study of the Present-Day Geodynamics of the Nizhnekansk Massif for Safe Disposal of Radioactive Wastes	2017/01/01	English	10