cladding

Examination of Fuel Elements Irradiated in the Reactor of the World’s First NPP After Long-Term Storage

9/23/2022 2022 - #03 Nuclear materials

Ivanov S.N. Porollo S.I. Shulepin S.V. Baranayev Yu.D. Timofeev V.F. Kharizomenov Yu.V.

Analyzing the causes for the dispersion of the fast reactor spent fuel pin cladding properties

9/30/2019 2019 - #03 Nuclear materials

Shemyakin V. N. Kinev E.A. Kozlov A.V. Portnykh I.A. Panchenko V.L. Evseev M.V.

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.

Inner fuel element corrosion of steels CHS68 and EK164 at fast power reactor on basis of uranium dioxide

10/23/2015 2015 - #03 Nuclear materials

Kinev E.A. Shikhalev V.S. Barybin A.V.