This paper presents the results of modeling heat fluxes from the outer surface of the KRO-200 container. The study was conducted for a temperature range of 40–150 °C. A comparison of the results was performed for coating materials characterized by different values of emissivity (ε = 0.4–0.95). The total heat release and its components – thermal radiation and convective heat transfer – were calculated. The aim of the study is to evaluate the temperature distribution on the outer surface of the KRO-200 container, which may affect its reliability, leak-tightness and durability. The modeling enabled the establishment of a relationship between the intensity of heat release and the parameters of heat exchange with the environment. The results confirm the importance of using adaptive technologies and monitoring systems to prevent local overheating or excessive cooling. The analysis serves as a basis for developing recommendations on optimizing container design and improving environmental safety during the long-term storage of liquid radioactive waste.
- Alokhina, S. V. (2018). Problems of creating scientific and methodological foundations for the thermal safety of dry storage of spent nuclear fuel in Ukraine. Journal of Mechanical Engineering, Vol. 21, Iss. 3, 4-12. https://doi.org/10.15407/pmach2018.03.004 (in Ukrainian)
- Nuclear technology review. Vienna: International Atomic Energy Agency, 2017. – 54 р.
- Afanasyev, A., Gromok, L., Pavelenko, V., Steinberg, N. (2004). Radioactive waste management in Ukraine: Status, problems, prospects. Fifty years of nuclear power. The next fifty years: Book of extended synopses, Vol. 35, Iss. 41, 139-140. (in Ukrainian)
- Zhyhalov, Ya. A., Pshenychnyi, V. A. (2014). Determination of the Attenuation Coefficient of the Ambient Dose Equivalent Rate of Gamma Radiation by the Shell Material of Cylindrical Containers for Temporary Storage of Liquid Radioactive Waste. Nuclear and Radiation Safety, 1, 34-44. (in Ukrainian)
- Radioactive waste management during the operation of NPPs of JSC "NNEGC "Energoatom": 2024 report. Available from: https://energoatom.com.ua/storage/activity/FhtuLX1BuOC6VSA58y2hpbmJKIH9KSANilvAcSPZ.pdf (in Ukrainian, accessed on May 25, 2026)
- Yang, X., Huang, B., Li T., Gan Y., Zhu Y., Zheng J. (2025). Effect of glass cooling method on thermal shock behavior of nuclear waste container. Kerntechnik, Vol. 90, № 3, 325-340. https://doi.org/10.1515/kern-2024-0133
- Li, T., Yang, X., Huang, B., Gan, Y., Zhu, Y., Zheng, J. (2025). Effect of pouring temperature and rate of glass on thermal shock behavior of nuclear waste container. Proceedings of the Institution of Mechanical Engineers, Part C, 239. 107-131. https://doi.org/10.1177/09544062241297117
- Meleichuk, S. S., Arseniev, V. M., Ivchenko, O. V. (2023). Heat and mass transfer. Sumy: Sumy State University. (in Ukrainian)
- Vasserman, O. A., Slynko, O. G., Malchevskyi, V. P. (2011). Fundamentals of heat and mass transfer. Odesa: Feniks. (in Ukrainian)
- Rymar, Т., Stanislavchuk, О., Rymar, О. (2025). Thermal flow modeling for predicting the cooling process of a liquid radioactive waste storage container. Bulletin of Lviv State University of Life Safety, 32, 141-147. https://doi.org/10.32447/20784643.32.2025.11 (in Ukrainian)
- Hanford nuclear site starts vitrifying radioactive waste into glass. Techno NV. Available from: https://techno.nv.ua/ukr/popscience/yaderniy-kompleks-henford-startuye-pererobka-radioaktivnih-vidhodiv-u-sklo-50550333.html (in Ukrainian, accessed on May 25, 2026)
- Uatom: Nuclear safety, radiation protection, and non-proliferation website. "Deep geological repository for radioactive waste to be built in France". Available from: https://uatom.org/2025/12/11/u-frantsiyi-pobuduyut-gliboke-shovishhe-radioaktivnih-vidhodiv.html?utm_source=copilot.com (in Ukrainian, accessed on May 25, 2026)
- Application of Thermal Technologies for Processing of Radioactive Waste. – Vienna: International Atomic Energy Agency, 2006. – 250 p. (IAEA-TECDOC-1527).
- Holt E., Oksa M., Banford A. (2023). Advancing Sustainability Practices through Innovation in LILW Pre-Disposal Radioactive Waste Management: Outcomes from the EURATOM PREDIS Project. Environmental Science, Engineering.