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

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Estimation of the systematic error constituents in the calculations of the critical systems by the Monte Carlo method by V. V. Galchenko, V. I. Makodym

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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. Galchenko, V. I. Gulik, I. I. Shlapak

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Constant support of physical calculations subsystem of in-core monitoring system “Voyage” by V. V. Galchenko, A. A. Mishin, I. I. Shlapak

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Burnup credit calculations for criticality safety justification for RBMK-1000 spent fuel of transport and storage systems by V. V. Galchenko, V. I. Macodym, V. V. Solovyov, V. V. Ilkovich

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