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S.N. Pelykh

Observed names: Pelykh, Sergii, S. N. Pelykh, S. Pelykh, S.M. Pelykh, Sergey Pelykh, С Н Пелых
ORCID: 0000-0003-1608-8089
Observed ORCID: 0000-0003-1608-8089
OpenAlex ID: A5016862945
A method for VVER-1000 fuel rearrangement optimization taking into account both fuel cladding durability and burnup
2013 · S.N. Pelykh, M.V. Maksimov, et al. · Nuclear Engineering and Design · 18
Cladding rupture life control methods for a power-cycling WWER-1000 nuclear unit
2011 · S.N. Pelykh, M.V. Maksimov · Nuclear Engineering and Design · 18
Principles of controlling fuel-element cladding lifetime in variable VVER-1000 loading regimes
2012 · M. V. Maksimov, S. N. Pelykh, et al. · Atomic Energy · 16
Grounds of VVER-1000 fuel cladding life control
2013 · S.N. Pelykh, M.V. Maksimov, et al. · Annals of Nuclear Energy · 14
Model of cladding failure estimation for a cycling nuclear unit
2009 · M.V. Maksimov, S.N. Pelykh, et al. · Nuclear Engineering and Design · 13
The prediction problems of VVER fuel element cladding failure theory
2016 · S.N. Pelykh, M.V. Maksimov, et al. · Nuclear Engineering and Design · 12
Improved Models and Method of Power Change of Npp Unit With Vver-1000
2017 · T. Foshch, S. Pelykh · Automation technological and business processes · 7
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Theory of Fuel Life Control Methods at Nuclear Power Plants (NPP) with Water-Water Energetic Reactor (WWER)
2012 · Sergey Pelykh, Maksim Maksimov · InTech eBooks · 4
Estimation of local linear heat rate jump values in the variable loading mode
2011 · S.N. Pelykh, R.L. Gontar, et al. · Nuclear Physics and Atomic Energy · 4
Method for evaluating the service life of VVER-1000 fuel-element cladding in different loading regimes
2010 · M. V. Maksimov, S. N. Pelykh, et al. · Atomic Energy · 2
The Change of Paradigm in Nuclear Fuel Optimization: From Conservatism to Synergy
2019 · Сергей Николаевич Пелых, S.N. Pelykh · Cambridge Scholars Publishing eBooks · 1
Models and Methods for Automated Control of Power Change at WWER1000
2018 · T. Foshch, M. Maksimov, et al. · Nuclear and Radiation Safety · 1
A method for VVER fuel element cladding reliability prediction
2014 · S.M. Pelykh, M.V. Maksimov, et al. · Nuclear Physics and Atomic Energy · 1
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Test-free detection and localization of Java defects with structural and semantic code representations: code, data and results
2026 · Maksymenko, Hlib, Pelykh, Sergii · Zenodo (CERN European Organization for Nuclear Research)
The cladding damage parameter under normal operating conditions in VVER fuel design: Resolving contradictions
2021 · S.N. Pelykh · Nuclear Engineering and Design
Research Nuclear Fuel Properties in a Vver-1000 Reactor During a Campaign and a Computer-integrated System Controlling the Fuel Properties
2020 · D.O. Tereshchenko, S.N. Pelykh · Scientific notes of Taurida National V I Vernadsky University Series Technical Sciences
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The physics and regularities of the neutron-thermoacoustic instability
2018 · S.N. Pelykh, Huiyu Zhou, et al. · Nuclear Physics and Atomic Energy
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Automated System for Control of Vver-1000 Fuel Properties Considering Fuel Cladding Damage Parameter
2018 · S. Pelykh, М. Frolov, et al. · Odes’kyi Politechnichnyi Universytet Pratsi
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The Problem of Minimizing the Radioactive Leakage Into the Vver Circuit Under Normal Conditions
2017 · S.N. Pelykh, М.А. Frolov, et al. · Odes’kyi Politechnichnyi Universytet Pratsi
Search for the Best Power Control Program at Npp With Vver-1000 Using Gradient Descent Method
2017 · S. N. Pelykh, E. A. Odrehovska, et al. · Automation technological and business processes
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An analysis of the fuel element cladding failure parameter considering the nonuniformity of energy release in a fuel assembly
2016 · S.N. Pelykh, M.V. Maksimov, et al. · Nuclear Physics and Atomic Energy
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A method for limitation of probability of accumulation of fuel elements claddings damage in WWER
2014 · S.N. Pelykh, M.V. Nikolsky, et al. · Odes’kyi Politechnichnyi Universytet Pratsi
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A Model of Fuel Rearrangement Optimization for a Vver-1000 Cycling Unit Considering Reactor Power Growth up to 110 %
2012 · S.N. Pelykh
Спосiб стабілізації аксіального розподілу нейтронного поля під час маневрування потужністю ВВЕР-1000
2011 · M. Maksimov, S. Pelykh, et al. · Nuclear and Radiation Safety
Mathematical model of fuel element cladding state change for a WWER-1000 plant operated in the mode of varying loading
2010 · S.N. Pelykh · Nuclear Physics and Atomic Energy
Works count: 30
Citation count: 111
H-index: 7
I10-index: 6
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