Methods and results of determining the impurity gas amount in ceramic fuel
Vityuk G. Vurim A. Skakov M. Pakhnits A.
January 2021Elsevier Ltd
Annals of Nuclear Energy
2021#150
An issue of estimating the impurity gas amount in fresh ceramic nuclear fuel is discussed from the point of view of their possible influence on parameters of in-pile experiments simulating a severe accident with core melting. A method based on measuring the pressure and temperature of gas in a closed cavity where fuel is fast melted is proposed and experimentally tested under in-pile experiment conditions. The fuel was melted due to internal energy release in the central experimental channel of the research impulse graphite reactor (IGR) during implementation of a controlled neutron impulse.
IGR reactor , Impurity gases , Melting , Nuclear fuel , Pressure
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Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakhstan, 071100, Kurchatov, 2 Beibyt Atom St., Kazakhstan
National Nuclear Center of the Republic of Kazakhstan, 071100, Kurchatov, 2 Beibyt Atom St., Kazakhstan
Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakhstan
National Nuclear Center of the Republic of Kazakhstan
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