thermocouple

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.

Calculations and experimental investigation of the irradiation rig with a fuel heater for the BOR-60 reactor

3/28/2016 2016 - #01 Physics and technology of nuclear reactors

Varivtcev A.V. Zhemkov I.Yu. Boev A.V. Ishunina O.V. Naboyshchikov Yu.V. Poglyad N.S. Sharonova M.G.