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

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

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Monte-Carlo Serpent code validation based on the experimental data from research subcritical facility by 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 by 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 by 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 by 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 by 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 by 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 by M. I. Holiuk, O. M. Khotiaintseva, V. M. Khotiaintsev, A. V. Nosovskyi, V. I. Hulik

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