Mathematical dependence for the 137Cs concentration in spent nuclear fuel and its using for experimental data processing

by V. V Galchenko, V. L. Diemokhin
Published 2013-06-01

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
Published 2009-09-01

Constant support of physical calculations subsystem of in-core monitoring system “Voyage”

by V. V. Galchenko, A. A. Mishin, I. I. Shlapak
Published 2018-06-01

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
Published 2016-12-01

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
Published 2010-12-01