Computational approaches for determining the nuclear heating value of structural materials during the irradiation at the IGR reactor
Kelsingazina R. Vityuk V. Vurim A. Vityuk G. Mukhamedov N. Tikhomirov G.
1 September 2024Elsevier Ltd
Annals of Nuclear Energy
2024#204
When conducting in-pile studies at the Impulse Graphite Reactor (IGR), it is necessary to have an information of the thermal state of the structural elements of the experimental device to ensure the safety of the experiment as well as to obtain the detailed data about the experiment predicted parameters. This paper presents the developed approach of the computer simulation to determine the nuclear heating value of the structural materials during their irradiation in reactor facility. The detailed neutronic and thermohydraulic calculations have been done to determine the main parameters of the irradiated samples of various structural materials used in nuclear industry. The validation of the calculated values of the temperature change of the samples with the experimentally obtained data at the IGR reactor has been carried out.
Computer simulation , Experimental data , In-pile study , Nuclear heating , Structural materials , Validation
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National Nuclear Center of the Republic of Kazakhstan, 180010, Kurchatov, 2 Beibyt Atom St., Kazakhstan
Shakarim University, 071412, Semey, 20A Glinka St., Kazakhstan
National Research Nuclear University “MEPhI”, 115409, Moscow, 31 Kashirskoe Shosse, Russian Federation
National Nuclear Center of the Republic of Kazakhstan
Shakarim University
National Research Nuclear University “MEPhI”
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