Spacer Grid Measurement of the spent fuel rod cladding temperature during the in pile testing at 500 – 900°c 11/28/2017 2017 - #04 Physics and technology of nuclear reactors Dreganov O.I. Shulimov V.N. Kiseleva I.V. Alekseev A.V. In service change in the flexural rigidity of the VVER 1000 fuel assemblies 10/02/2016 2016 - #03 Nuclear materials Pavlov S.V. Fluid flow and heat transfer in fuel rods assembly with modified spacer grids 10/23/2015 2015 - #03 Thermal physics and thermal hydraulics Krapivtsev V.G. Markov P.V. Solonin V.I. Combined numerical and experimental investigations of hydrodynamics and coolant flow mass transfer out of spacer grid in fuel assemblies of floating power unit 12/29/2014 2014 - #04 Thermal physics and thermal hydraulics Doronkov D.V. Pronin A.N.