Leskin Sergei Terent’evich Professor, Dr. Sci. (Engineering) IATE MEPhI firstname.lastname@example.orgPreliminary Assessment of the Characteristics of Brayton Cycle Equipment at Supercritical CO2 Parameters 3/28/2023 2023 - #01 Nuclear power plants Leskin S.T. Slobodchuk V.I. Shelegov A.S. Soloviev D.S.Computational Analysis of the Power Conversion Loop of a Nuclear Power Plant Unit with the Closed S-CO2 Brayton Cycle 9/23/2022 2022 - #03 Nuclear power plants Leskin S.T. Slobodchuk V.I. Shelegov A.S.Identifying the Key Development Areas for Small Modular Reactors 1/20/2022 2022 - #01 Nuclear power plants Soloviev S.L. Zaryugin D.G. Kalyakin S.G. Leskin S.T.Determination of 18-month fuel cycle parameters with goal of fuel costs minimization at the basis of use constructions of fuel assemblies in VVER-1200 reactors 9/20/2018 2018 - #03 Fuel cycle and nuclear waste management Hashlamoun T.M. Vygovskiy S.B. Leskin S.T. Analysis of acoustic signals of leak for increases in sensitivity of control due to creation of effective diagnostic features 3/23/2018 2018 - #01 Global safety, reliability and diagnostics of nuclear power installations Shvetsov D.M. Trykov E.L. Leskin S.T. Puzakov A.Yu.Analisys of safety system pump condition based on their testing results 3/22/2017 2017 - #01 Global safety, reliability and diagnostics of nuclear power installations Leskin S.T. Slobodchuk V.I. Shelegov A.S. Kashin D.Yu.Analisys of VVER-1000 main circulation pump condition under operation 12/25/2016 2016 - #04 Nuclear power plants Leskin S.T. Slobodchuk V.I. Shelegov A.S.Numerical simulation of the coolant flow in the porous body model of a fast breeder reactor 12/29/2013 2013 - #04 Modelling processes at nuclear facilities Leskin S.T. Slobodchuk V.I. Shelegov A.S. Yaurov S.V. Chistozvonova E.A. Sorokin A.P. Opanasenko A.N. Kalyakin S.G. Zaryugin D.G.Numerical and experimental investigations of thermalhydraulic characteristics for fast reactor vessals on integral model SARH in different operation regimes 7/14/2013 2013 - #02 Thermal physics and thermal hydraulics Zaryugin D.G. Kalyakin S.G. Leskin S.T. Opanasenko A.N. Sorokin A.P.Software Analysis of in!core monitoring system and reporting on the state of the reactor core of VVER-1000 KARUND 5/29/2012 2012 - #01 Physics and technology of nuclear reactors Leskin S.T.