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The Institute of Atomic Energy of the National Nuclear Center of the Republic of Kazakhstan has been conducting research on fuel assemblies (FAs) for thermal and fast nuclear power reactors for many years. Such research is possible thanks to the availability of a unique experimental base, represented by the IVG.1M and IGR research reactors and other experimental complexes and stands [1]. In addition to experimental work, such research is accompanied by computer analysis of the main neutron-physical and thermophysical characteristics of both the experimental device and the installation itself.
This paper presents the approaches and methods used for computational fluid dynamics (CFD) modeling of the state of experimental devices tested in the core of the IGR research reactor.
The IGR research pulse graphite reactor is a facility with unique characteristics: (1) thermal neutron fluence reaching 3.7·1016 n/cm2, (2) thermal neutron flux density equal to 7·1016 n/(cm2·s). These technical characteristics make it possible to simulate the behavior of fuel assemblies (FAs) in power reactors both under normal operating conditions and in the event of severe accidents.
CFD modeling is a powerful tool that allows for high-quality reproduction of real physical processes. The quality of modeling is ensured by adherence to proven and tested methodologies (Figure 1).
A distinctive feature of CFD analysis is the ability to calculate the behavior of fluid coolants (water, liquid metal) and gas coolants, as well as to simulate the formation and movement of molten nuclear fuel and structural materials in an experimental device during a simulated reactor test. Thus, modern computer methods for modeling complex physical processes make it possible to solve real problems in the nuclear industry, thereby improving the safety of existing and future nuclear reactors.
This work was supported by the Science Committee of the Ministry of Science and Higher Education of the Republic of Kazakhstan (Grant No. AP19577709).
