Simulation of industrial 60So gamma-ray source by Monte-Carlo method von V. I. Hulik

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Simulation of fuel distribution in the inner fast zone for two-zone subcritical reactor von V. I. Hulik

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Monte-Carlo Serpent code validation based on the experimental data from research subcritical facility von O. R. Trofymenko, A. V. Nosovskyi, V. I. Hulik

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Using of the Serpent code based on the Monte-Carlo method for calculation of the VVER-1000 fuel assembly characteristics von V. V. Halchenko, V. I. Hulik, I. I. Shlapak

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Investigation of Novel Composite Material Based on Extra¬Heavy Concrete and Basalt Fiber for Gamma Radiation Protection Properties von I. M. Romanenko, M. I. Holiuk, A. V. Nosovskyi, V. I. Hulik

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Cross-verification of Monte Carlo codes Geant4 and MCNP6 for muon tomography von Kh. V. Hrytsiuk, A. M. Bozhuk, A. V. Nosovskyi, V. I. Hulik

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New composite material based on heavy concrete and basalt¬boron fiber for neutron radiation shielding properties von I. M. Romanenko, M. I. Holiuk, A. V. Nosovskyi, T. S. Vlasenko, V. I. Hulik

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Monte Carlo code Serpent calculation of the parameters of the stationary nuclear fission wave von V. M. Khotiaintsev, V. I. Hulik, O. M. Khotiaintseva, A. V. Aksonov, V. M. Pavlovych

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The optimization of calculation time and statistical error for the radiation shielding properties simulation of containers for storage of spent nuclear fuel von M. I. Holiuk, O. M. Khotiaintseva, V. M. Khotiaintsev, A. V. Nosovskyi, V. I. Hulik

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