Experimental Study of the Effects of a Constant and Variable Electric Fields on the Strength Properties of the Blade Steel Surface Layer von Nechaev, A.V.

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Wet Steam Flow Ionization and Prospects to Practically Apply Electrical Discharge Devices in Turbo Installations von Tarelin, A.O., Annopolska, I.Ye.

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Re-Extension of 200 MW Turbine Cast Casing Service von Chernousenko, O.Yu., Ryndyuk, D.V., Peshko, V.A.

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Tete-a-tete project: software engineering tools supporting understanding von Hrytsay, V.P., Zakhariya, L.M.

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Digital Program Control and Complex Component Processing in Performance-Driven Production Engineering von Petrova, Desislava, Balabanova, Ivelina, Georgiev, Georgi

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RENEWABLE ENERGY SOURCES IN ELECTRIC-POWER INDUSTRY OF NAKHCHIVAN AUTONOMOUS REPUBLIC von Rzayev, M. A., Novruzova, S. Y.

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Numerical Simulation of Metal Hydride Battery Heat Conducting Matrix Heat-stressed and Deformed State von Avramenko, A.N., Levterov, A.M., Gladkova, N.Yu.

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Basic Operation Principles and Control Algorithm for a High-pressure Membrane-less Electrolyser von Solovei, V.V., Kotenko, A.L., Vorobiova, I.O., Shevchenko, A.A., Zipunnikov, M.M.

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Modeling Heat and Mass Exchange Processes in Metal-hydride Installations von Chorna, N.A., Hanchyn, V.V.

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Peculiarities of Identifying a Power-generating Single-shaft GTE Mathematical Model von Lyutikov, A.L.

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Ecosystem research in software engineering von Sydorov, N.A.

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ENGINEERING-GEOLOGICAL INVESTIGATIONS IN THE SYSTEM OF EARTH SCIENCES OF NAS OF UKRAINE von Demchyshyn, M.G., Kril, T.V.

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Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method von Rudychev, V.G., Azarenkov, N.A., Girka, I.O., Rudychev, Y.V.

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The efficiency assessment of the state system of nuclear safety control of NSC-SO von Godun, R.L., Doroshenko, A.O., Muliar, D.О.

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Scientific basis of thermal safety analysis of dry storage of spent nuclear fuel on zaporizhska NPP von Alyokhina, S., Kostikov, A., Koriahina, I.

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Methodology and results of thermal calculation of one-through steam generators for NPP of small power von Kravchenko, V.P., Xiaolong Zhou

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The development of a three-dimensional model of WWER-1000 core using the Monte Carlo Serpent code for neutron-physical modeling von Gulik, V.I., Trofymenko, O.R., Galchenko, V.V., Budik, D.V.

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Choice of basic construction parameters of steam generators for NPP of low power von Kravchenko, V.P., Sereda, R.M., Zhou Xiaolong, Visotskii, Yu.I., Rybakov, А.Н.

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Combined calculation of radiation from large-sized ground RW storage facilities on the basis of Monte Carlo method von Rudychev, V.G., Azarenkov, N.A., Girka, I.O., Rudychev, D.V., Rudychev, Y.V.

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Comparative analysis of numerical methods used for thermal modeling of spent nuclear fuel dry storage systems von Alyokhina, S., Matsevity, Y., Dudkin, V., Poskas, R., Sirvydas, A., Rackaitis, K., Zujus, R.

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