Title	Publication Date	Language	Citations
Plasma separation of the elements applied to nuclear materials handling	2006/10/01	English	52
Molten-salt reactors: new possibilities, problems and solutions	2012/07/01	English	49
Conceptual framework of a strategy for the development of nuclear power in Russia to 2100	2012/10/01	English	48
Enrichment of Regenerated Uranium with Simultaneous Dilution of 232–236U by Raw and Waste Uranium	2014/10/14	English	41
Multistream Cascades for Separation of Multicomponent Isotopic Mixtures	2015/12/01	English	36
Modernization of the IBR-2 pulsed research reactor	2012/10/18	English	32
PuF3, AmF3, CeF3, and NdF3 Solubility in LiF–NaF–KF Melt	2013/10/20	English	29
Neutron Yield of the Reaction (α, n) on Thick Targets Comprised of Light Elements	2015/02/18	English	29
Nuclear-Magnetic Flowmeter-Relaxometers for Monitoring Coolant and Feedwater Flow and Status in Npp	2020/03/01	English	28
Enrichment of Regenerated Uranium in a Gas Centrifuge Cascade with Simultaneous Dilution of 232,236U by Waste and Low-Enrichment Uranium	2017/09/01	English	26
Experimental Studies of the Characteristics of Contact Heat Exchange Between Lead Coolant and the Working Body	2005/03/01	English	23
Concept of an advanced power-generating unit with a BN-1200 sodium-cooled fast reactor	2010/08/01	English	22
Fuel Salt for the Molten-Salt Reactor	2013/10/20	English	22
Reprocessed uranium purification in cascades with 235U enrichment to 5%	2013/10/20	English	21
Optimization of a Centrifuge Cascade for Separating a Multicomponent Mixture of Isotopes	2013/11/14	English	21
Composition Optimization of Homogeneous Radiation-Protective Materials for Planned Irradiation Conditions	2017/02/01	English	21
Technical solutions and development stages for the BREST-OD-300 reactor unit	2012/10/18	English	20
Prospects for Using Nitride Fuel in Fast Reactors with a Closed Nuclear Fuel Cycle	2014/11/30	English	20
Impurities and their effect on the structure and properties of zirconium parts in nuclear reactors	2008/11/01	English	19
Fuel Pin Melting in a Fast Reactor and Melt Solidification: Simulation Using the SAFR/V1 Module of the EVKLID/V2 Integral Code	2018/07/01	English	19
Experimental validation of the cooling loop for a passive system for removing heat from the AES-2006 protective envelope design for the Leningradskaya nuclear power plant site	2009/03/01	English	19
Neutron-physical characteristics of a VVÉR core with 100% load of reprocessed uranium and plutonium fuel	2006/12/01	English	18
Identification of the Main Dose-Forming Radionuclides in NPP Emissions	2016/05/27	English	18
Correcting the isotopic composition of regenerated uranium with respect to 232U by a centrifuge method with introduction of a carrier gas	2008/09/01	English	17
High-purity titanium, zirconium, and hafnium in nuclear power	2011/12/01	English	17
Decommissioning Features of BN-350, -600 Fast Reactors	2019/02/01	English	17
SAFR/V1 (EVKLID/V2 Integral Code Module) Aided Simulation of Melt Movement Along the Surface of a Fuel Element in a Fast Reactor During a Serious Accident	2018/08/01	English	17
MCU-PTR program for high-precision calculations of pool and tank type research reactors	2011/01/01	English	17
Molten-Salt Reactor for Nuclear Fuel Cycle Closure on All Actinides	2019/03/01	English	16
Brest Lead-Cooled Fast Reactor: From Concept to Technological Implementation	2021/02/01	English	16