Kalyakin Sergey Georgievich

Director of Department, Dr. Sci. (Engineering)

All-Russian Research Institute for Nuclear Power Plants Operation JSC

SGKalyakin@vniiaes.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.

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.

Features of technology of purification from impurities of high-temperature sodium coolant in a fast reactor for hydrogen production and other innovative applications

12/25/2016 2016 - #04 Nuclear materials

Kozlov F.A. Kalyakin S.G. Sorokin A.P. Alekseev V.V. Trufanov A.A. Konovalov M.A. Orlova E.A.

Investigations for the substantiation of high-temperature nuclear power generation technology using fast sodiumcooled reactor for hydrogen production and other innovative applications (part 1)

10/02/2016 2016 - #03 Physics and technology of nuclear reactors

Kalyakin S.G. Kozlov F.A. Sorokin A.P. Bogoslovskaya G.P. Ivanov A.P. Konovalov M.A. Morozov A.V. Stogov V.Yu.

Studies validating a sodium purification system integrated in the reactor vessel

7/14/2014 2014 - #02 Thermal physics and thermal hydraulics

Kalyakin S.G. Sorokin A.P. Kozlov F.A. Alekseev V.V. Scherbakov S.I.

Innovative nuclear power technology – the basis of large-scale nuclear power engineering

5/29/2014 2014 - #01 Current issues in nuclear energy

Rachkov V.I. Kalyakin S.G.

Thermohydraulical researches NPP (to the 60 anniversary of the first NPP)

5/29/2014 2014 - #01 Current issues in nuclear energy

Rachkov V.I. Efanov A.D. Zhukov A.V. Kalyakin S.G. Sorokin A.P.

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.