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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. Solntsev D.N. Sorokin V.D. Khrobostov A.E.