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Konstantin Sergeenko
Konstantin Sergeenko
JSC NIKIET
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Title
Cited by
Cited by
Year
Demonstration of the model of physicochemical processes in heavy liquid metal cooled reactors in an example of the THEADES experiment simulation
K Sergeenko, K Svirid, D Afremov, V Folomeev
Nuclear Engineering and Design 395, 111870, 2022
62022
LES-simulation of heat transfer in a turbulent pipe flow with lead coolant at different Reynolds numbers
KM Sergeenko, VM Goloviznin, VY Glotov
42018
A study of thermophysical and physicochemical characteristic of the KALLA experiment facility
K Sergeenko, K Svirid, V Nikolaev, D Afremov, A Tutukin, I Sapozhnikov
Nuclear Engineering and Design 414, 112475, 2023
12023
Adaptation of the Turbulence Model to the Heat Transfer in a Hexagonal Rod Bundle
K Sergeenko
Available at SSRN 4134182, 2022
12022
Direct numerical simulation of turbulent flow and heat transfer in a hexagonal rod bundle
KM Sergeenko, AY Chulyunin, BI Krasnopolsky
Journal of Physics: Conference Series 1369 (1), 012045, 2019
12019
LES simulation of heat transfer in a turbulent pipe flow with lead coolant at different Reynolds numbers
KM Sergeenko, VM Goloviznin, VY Glotov
Mathematical Models and Computer Simulations 11, 176-189, 2019
12019
Numerical simulation of hydraulics and heat transfer in the BREST-OD-300 LFR fuel assembly
D Fomichev, D Afremov, A Tutukin, V Smirnov, K Sergeenko
12017
Adaptation of the turbulence model to the heat transfer in a rod bundle
K Sergeenko
Nuclear Engineering and Design 415, 112664, 2023
2023
Mathematical Modeling of Water Flow Through a Broad-Crested Spillway Using the CFD Code Star-CCM+
KM Sergeenko, VV Malakhanov, AR Belousov, IN Vishnyakov, NS Karpov, ...
Power Technology and Engineering 52 (5), 534-540, 2019
2019
Application of CFD simulation to validate the BREST-OD-300 primary circuit design
AV Tutukin, DA Afremov, KM Sergeenko, DV Fomichev
2018
Application of CFD simulation to design substantiation of the BREST-OD-300 lead
A Tutukin, K Sergeenko, D Fomichev, D Afremov
2017
CFD simulation of heat exchange in conditions of a cross flow around the tube bundle with regard for thermal contact resistance
KM Sergeenko, DA Afremov, AV Tutukin, DA Ognerubov, DV Fomichev
Innovative designs and technologies of nuclear power. IV International …, 2016
2016
Development of a model for the protective oxide film formation on the HLMC reactor primary circuit surfaces and its integration into CFD codes
KM Sergeenko, DA Afremov, DV Fomichev, EV Yurmanov, EA Varseev
Innovative designs and technologies of nuclear power. IV International …, 2016
2016
LES-simulation of heat transfer in a turbulent pipe
K Sergeenko, V Goloviznin, V Glotov
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