Аңдатпа
In this article, we present the results of the creation of an information-analytical system (IAS) developed as a tool for research and prediction of the behavior of the corium simulating a core melt of a nuclear reactor in the experiments. This was carried out to justify the safety of the use of nuclear energy according to specific requirements of a customer. The data loaded into the IAS were obtained on the basis of the National Nuclear Center of the Republic of Kazakhstan (NNC) as a result of modeling the processes occurring during severe accidents at nuclear installations. The experimental data obtained at the benches of NNC and characterizing the processes occurring during the interaction of the core melt of the nuclear reactor with coolants, structural materials and structural elements of nuclear reactors were classified and structured for the convenience of analyzing and processing the data obtained. The structure of the created IAS is shown and the analytical block is described in detail.