DEVELOPMENT OF A THERMOPHYSICAL MODEL FOR THE EXPERIMENTAL ASSEMBLY OF THE VCG-135 TEST BENCH TO STUDY THE INTERACTION OF CORIUM WITH METAL-COOLER IN THE CONDITIONS OF A SEVERE ACCIDENT

This article presents the results of modeling of the temperature field of the experimental assembly of the VCG-135 test bench to study the interaction between model corium and candidate metal-coolers (zinc, antimony and manganese) in the conditions of a severe accident. The need for modeling is associated with the probability of metal melting in the discharge device due to the heat flow from the heating crucible of the experimental assembly. Thus, the purpose of the modeling was the justification of the integrity of the design of the metal discharge device during the production of liquid corium in the crucible of the experimental assembly. The thermophysical model was created in the ANSYS software. The temperature field of the experimental assembly was obtained at the moment of obtaining liquid corium as a result of the modeling. An analysis of the results showed that metal in the discharge device wouldn’t reach the melting point. In this regard, the discharge device of the experimental assembly can be used in its current design for experiments conducting at the VCG-135 test bench. At the same time, after the experiments, the thermophysical model was validated by comparing the calculated temperature values with experimental data. Validation of the model shows that the deviation of calculated and experimental temperature values at control points does not exceed acceptable limits (melting of the studied metal before interaction with corium). Thus, the developed thermophysical model can be used to justify further experiments on the VCG-135 test bench with the current experimental assembly.

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Publication Details

Journal
NNC RK Bulletin
Published
2024-12-30
DOI
https://doi.org/10.52676/1729-7885-2024-4-5-11
Primary Topic
Nuclear Materials and Properties
Type
article
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article

DEVELOPMENT OF A THERMOPHYSICAL MODEL FOR THE EXPERIMENTAL ASSEMBLY OF THE VCG-135 TEST BENCH TO STUDY THE INTERACTION OF CORIUM WITH METAL-COOLER IN THE CONDITIONS OF A SEVERE ACCIDENT

Maxat Bekmuldin, Маzhyn Skakov, Kuanyshbek Toleubekov, Assan Akaev
NNC RK Bulletin
Nuclear Materials and Properties
article

DEVELOPMENT OF A THERMOPHYSICAL MODEL FOR THE EXPERIMENTAL ASSEMBLY OF THE VCG-135 TEST BENCH TO STUDY THE INTERACTION OF CORIUM WITH METAL-COOLER IN THE CONDITIONS OF A SEVERE ACCIDENT

Maxat Bekmuldin, Маzhyn Skakov, Kuanyshbek Toleubekov, Assan Akaev
article en

Abstract

This article presents the results of modeling of the temperature field of the experimental assembly of the VCG-135 test bench to study the interaction between model corium and candidate metal-coolers (zinc, antimony and manganese) in the conditions of a severe accident. The need for modeling is associated with the probability of metal melting in the discharge device due to the heat flow from the heating crucible of the experimental assembly. Thus, the purpose of the modeling was the justification of the integrity of the design of the metal discharge device during the production of liquid corium in the crucible of the experimental assembly. The thermophysical model was created in the ANSYS software. The temperature field of the experimental assembly was obtained at the moment of obtaining liquid corium as a result of the modeling. An analysis of the results showed that metal in the discharge device wouldn’t reach the melting point. In this regard, the discharge device of the experimental assembly can be used in its current design for experiments conducting at the VCG-135 test bench. At the same time, after the experiments, the thermophysical model was validated by comparing the calculated temperature values with experimental data. Validation of the model shows that the deviation of calculated and experimental temperature values at control points does not exceed acceptable limits (melting of the studied metal before interaction with corium). Thus, the developed thermophysical model can be used to justify further experiments on the VCG-135 test bench with the current experimental assembly.

NNC RK Bulletin(4)
National Nuclear Center of the Republic of Kazakhstan (KZ), Institute of Atomic Energy (PL), Shakarim University (KZ)
Openalex Percentile: Top 83%
Nuclear Materials and Properties
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