Study of Spent Fuel Behavior in Beyond Design-Basis Storage Period von V. V. Halchenko

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Comparative Analysis of Reactor Cycle Neutron Characteristics Using Different WIMSD5B Nuclear Data Libraries von V. V. Halchenko, A. A. Mishyn

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Mathematical dependence for the 137Cs concentration in spent nuclear fuel and its using for experimental data processing von V. V. Halchenko, V. L. Diemokhin

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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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