fuel element

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.

Real-Time Temperature Field Recovery of a Heterogeneous Reactor Based on the Results of Calculations in a Homogeneous Core

1/20/2022 2022 - #01 Thermal physics and thermal hydraulics

Kuzevanov V.S. Podgorny S.K.

Features of Methods for Monitoring the Tightness of the Cladding of Fuel Elements in Fast Breeder Reactors with Lead Coolant

9/23/2021 2021 - #03 Global safety, reliability and diagnostics of nuclear power installations

Dragunova A.V. Morkin M.S. Perevezentsev V.V.

Rapid Preliminary Modeling of Floating NPP Cores

11/19/2020 2020 - #04 Physics and technology of nuclear reactors

Korolev V.I.

Development of a criterion to record the facts of fuel carryover from leaking fuel elements during VVER reactor operation

9/16/2020 2020 - #03 Nuclear power plants

Evdokimov I.A. Khromov A.G. Kalinichev P.M. Likhanskij V.V. Kovalishin A.A. Laletin M.N.

Galvanic corrosion of zirconnium alloys in water coolant

7/09/2020 2020 - #02 Nuclear materials

Melehovets A.Y. Pyshin I.V.

A study of the gas-water mixture in the rod control cluster assembly sleeve cavity of the RBMK-1000 reactor

3/23/2018 2018 - #01 Physics and technology of nuclear reactors

Belozerov V.I. Milinchuk V.K.

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.

Specifics of calculation of heat rate in oxide nuclear fuel during tests in reactor BOR-60

12/29/2014 2014 - #04 Thermal physics and thermal hydraulics

Varivtcev A.V. Zhemkov I.Yu.