Open Science Harvester of NAS of Ukraine

Застосування методів інтервального аналізу для оцінки безпеки і надійності енергоблоків АЕС

by Potanina, T., Yefimov, O., Harkusha, T., Yesypenko, T.
Published 2018

Determination of the dependence of the NPP unit power on the steam temperature at the outlet of the superheater separator first stage with an uncertainty of information

by Yefimov, O.V., Potanina, Т.V.
Published in Вопросы атомной науки и техники (2022)

Estimation of the dependence parameters of nuclear structural materials hardness on the content of gas impurities: an interval approach

by Potanina, Т.V., Yefimov, O.V., Pylypenko, M.M.
Published in Вопросы атомной науки и техники (2021)

Удосконалення властивостей оболонок твелів для вітчизняного ядерного паливного циклу

by Yefimov, O., Pylypenko, M., Kravchenko, V., Liubchik, L., Potanina, T., Yesypenko, T., Harkusha, T.
Published 2022

Кореляційна схема кадрової синхронізації у системах зв'язку з QPSK-модуляцією

by Sadchenko, A. V., Kushnirenko, O. A., Yefimov, O. I., Punko, V. V., Parovyi, S. Y.
Published 2017

Interval models of temperature characteristics of superheater separators in nuclear power plant units with the capacity of 1000 MW

by Yefimov, O.V., Potanina, T.V., Kavertsev, V.L., Harkusha, T.A., Yesypenko, Т.O.
Published in Вопросы атомной науки и техники (2022)

Computer simulation of thermal and hydraulic processes in NPP steam generator channels on the basis of interval-iterative method

by Yefimov, O.V., Pylypenko, M.M., Potanina, T.V., Kavertsev, V.L., Harkusha, T.A., Yesypenko, T.O.
Published in Вопросы атомной науки и техники (2022)

Mathematical relations of models of single-phase flows in the channels of reactors and steam generators of NPP's for calculation of heat transfer processes and hydrodynamic charact...

by Yefimov, O.V., Pylypenko, M.M., Kavertsev, V.L., Harkusha, T.A., Tiutiunyk, L.J., Motovilnik, A.V.
Published in Вопросы атомной науки и техники (2022)

The method for optimizing the iron content in the structural material Zr1%Nb for fuel element cladding of NPP nuclear reactors

by Yefimov, O.V., Pylypenko, M.M., Lyubchyk, L.M., Potanina, T.V., Kravchenko, V.P., Yesypenko, T.O., Harkusha, T.A.
Published in Problems of Atomic Science and Technology (2023)