Efficiency of various materials application for radiation shielding at transportation and storage of spent nuclear fuel by dry method by 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 by Godun, R.L., Doroshenko, A.O., Muliar, D.О.

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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 by 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 by 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 by Rudychev, V.G., Azarenkov, N.A., Girka, I.O., Rudychev, D.V., Rudychev, Y.V.

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Spent nuclear fuel dry storage: status and current issues by Yatsenko, M.V., Korolyov, A.V.

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The transmutation modeling for plutonium and minor actinides in the two-zone subcritical reactor by Gulik, V.I., Sheliahovskyi, D.O., Nosovskyi, A.V.

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Use of the Monte Carlo Serpent code for modeling the second series of experimental data of KUCA subcritical installation by Trofymenko, O.R., Nosovsky, А.V., Gulik, V.I.

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Construction problems of volume protected by airtermination rod for the ukrainian nuclear power plant under standard EN 62305 by Istomin, О.Ye., Koliushko, D.G., Kiprych, S.V., Rudenko, S.S.

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