Research article

Information-analytical system as a tool for research and prediction of the behavior of the melt of the core of a nuclear reactor

  • Received: 06 August 2023 Revised: 25 October 2023 Accepted: 08 November 2023 Published: 28 November 2023
  • 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.

    Citation: Alexander Vurim, Yuliya Baklanova, Nuriya Mukhamedova, Andrey Syssaletin, Ramil Islamov. Information-analytical system as a tool for research and prediction of the behavior of the melt of the core of a nuclear reactor[J]. AIMS Materials Science, 2023, 10(6): 1034-1044. doi: 10.3934/matersci.2023055

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  • 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.



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    [1] Vurim A, Mukhamedova N, Baklanova Y, et al. (2023) Information and analytical system as a promising database used to justify the safety of nuclear energy. Nucl Eng Des 415: 112704. https://doi.org/10.1016/j.nucengdes.2023.112704 doi: 10.1016/j.nucengdes.2023.112704
    [2] Mikhailov A (2020) Analiz osnovopolagayushchikh printsipov informatsionno-analiticheskikh sistem. Int J Hum Nat Sci 45: 45–48 (in Russian). https://doi.org/10.24411/2500-1000-2020-10695 doi: 10.24411/2500-1000-2020-10695
    [3] Nasiri F, Ooka R, Haghighat F, et al. (2022) Data analytics and information technologies for smart energy storage systems: A state-of-the-art review. Sustain Cities Soc 84: 104004. https://doi.org/10.1016/j.scs.2022.104004 doi: 10.1016/j.scs.2022.104004
    [4] Mukhamedov N, Skakov M, Deryavko I, et al. (2017) Thermal properties of prototype corium of fast reactor. Nucl Eng Des 322: 27–31. https://doi.org/10.1016/j.nucengdes.2017.06.026 doi: 10.1016/j.nucengdes.2017.06.026
    [5] Tskhe V, Mukhamedov N, Gaydaychuk V, et al. (2022) The method of the reactivity margin calculation required for the IGR reactor start-up in the "Pulse" mode. Ann Nucl Energy 168: 108875. https://doi.org/10.1016/j.anucene.2021.108875 doi: 10.1016/j.anucene.2021.108875
    [6] Hofmann P, Hagen S, Noack V, et al. (2017) Chemical-physical behavior of light water reactor core components tested under severe reactor accident conditions in the CORA facility. Nucl Technol 118: 200–224. https://doi.org/10.13182/NT118-200 doi: 10.13182/NT118-200
    [7] Andersona M, Herranzb L, Corradini M (1998) Experimental analysis of heat transfer within the AP600 containment under postulated accident conditions. Nucl Eng Des 185: 153–172. https://doi.org/10.1016/S0029-5493(98)00232-5 doi: 10.1016/S0029-5493(98)00232-5
    [8] Skakov M, Mukhamedov N, Deryavko I, et al. (2017) Research of structural-phase state of natural corium in fast power reactors. Vacuum 141: 214–221. https://doi.org/10.1016/j.vacuum.2017.04.022 doi: 10.1016/j.vacuum.2017.04.022
    [9] Rouge S (1997) SULTAN test facility for large-scale vessel coolability in natural convection at low pressure. Nucl Eng Des 169: 185–195. https://doi.org/10.1016/S0029-5493(96)01277-0 doi: 10.1016/S0029-5493(96)01277-0
    [10] Asmolov V, Ponomarev-Stepnoy N, Strizhov V, et al. (2001) Challenges left in the area of in-vessel melt retention. Nucl Eng Des 209: 87–96. https://doi.org/10.1016/S0029-5493(01)00391-0 doi: 10.1016/S0029-5493(01)00391-0
    [11] Journeau C, Piluso P, Haquet J, et al. (2009) Two-dimensional interaction of oxidic corium with concretes: The VULCANO VB test series. Ann Nucl Energy 36: 1597–1613. https://doi.org/10.1016/j.anucene.2009.07.006 doi: 10.1016/j.anucene.2009.07.006
    [12] Skakov M, Mukhamedov N, Deryavko I, et al. (2017) Thermal properties and phase composition of full-scale corium of fast energy reactor. Key Eng Mater 736: 58–62. https://doi.org/10.4028/www.scientific.net/KEM.736.58 doi: 10.4028/www.scientific.net/KEM.736.58
    [13] Vurim A, Mukhamedova N, Baklanova Y, et al. (2022) Information and analytical system for processing of research results to justify the safety of atomic energy. Appl Sci 19: 9705. https://doi.org/10.3390/app12199705 doi: 10.3390/app12199705
    [14] Vara J, Marcos E (2023) A framework for model-driven development of information systems: Technical decisions and lessons learned. J Syst Software 85: 2368–2384. https://doi.org/10.1016/j.jss.2012.04.080 doi: 10.1016/j.jss.2012.04.080
    [15] Biswal B, Duncan A, Sun Z (2022) ADA: Advanced data analytics methods for abnormal frequent episodes in the baseline data of ISD. Nucl Eng Technol 54: 3996–4004. https://doi.org/10.1016/j.net.2022.07.006 doi: 10.1016/j.net.2022.07.006
    [16] Mukhamedov N, Kozhakhmetov Y, Tskhe V (2022) Microstructure and mechanical properties of the solidified melt obtained by the in-pile test. Ann Nucl Energy 179: 109404. https://doi.org/10.1016/j.anucene.2022.109404 doi: 10.1016/j.anucene.2022.109404
    [17] Vialetto G, Noro M (2020) An innovative approach to design cogeneration systems based on big data analysis and use of clustering methods. Energ Convers Manage 214: 112901. https://doi.org/10.1016/j.enconman.2020.112901 doi: 10.1016/j.enconman.2020.112901
    [18] Moreau C, Legroux С, Peralta M (2022) Mining SQL workloads for learning analysis behavior. Inform Syst 108: 102004. https://doi.org/10.1016/j.is.2022.102004 doi: 10.1016/j.is.2022.102004
    [19] Saggi M, Jain S (2018) A survey towards an integration of big data analytics to big insights for value-creation. Inform Process Manag 54: 758–790. https://doi.org/10.1016/j.ipm.2018.01.010 doi: 10.1016/j.ipm.2018.01.010
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