Leskin Sergei Terent’evich

Head of Department, Professor, Dr. Sci. (Engineering)

IATE MEPhI

STLeskin@mephi.ru

New Technical Solutions for the Design of NPP Passive Safety Systems

3/18/2024 2024 - #01 Global safety, reliability and diagnostics of nuclear power installations

Soloviev S.L. Zaryugin D.G. Kalyakin S.G. Leskin S.T. Soloviev D.S.

Preliminary 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.