PSI - Issue 59

Yaroslav Dubyk et al. / Procedia Structural Integrity 59 (2024) 36–42 Dubyk and Zvirko/ Structural Integrity Procedia 00 (2019) 000 – 000

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Acknowledgements First author would like to acknowledge colleagues from NEA Task Group on the RPV Integrity Assessment for In-Vessel Retention (Status Report). Fruitful discussion during the meeting motivated and encouraged the paper writing. References Bechta, S. V., Granovsky, V. S., Khabensky, V. B., Krushinov, E. V., Vitol, S. A., Strizhov, V. F., Bottomley, D., Fischer, M., Piluso, P., Miassoedov, A., Tromm, W., Altstadt, E., Willschutz, H. G., Fichot, F., Kymalainen, O., 2008. VVER steel corrosion during in-vessel retention of corium melt, 3rd European Review Meeting on Severe Accident Research (ERMSAR-2008), Nesseber, Bulgaria, Paper 2-7. Bechta, S. V., Granovsky, V. S., Khabensky, V. B., Krushinov, E. V., Vitol, S. A., Sulatsky, A. A., Gusarov, V. V., Almiashev, V. I., Lopukh, D. B., Bottomley, D., Fischer, M., Piluso, P., Miassoedov, A., Tromm, W., Altstadt, E., Fichot, F., Kymalainen, O., 2009. VVER vessel steel corrosion at interaction with molten corium in oxidizing atmosphere. Nuclear Engineering and Design 239(6), 1103-1112. https://doi.org/10.1016/j.nucengdes.2008.12.009 Bechta, S., Khabensky, V., Granovsky, V., Krushinov, E., Vitol, S., Gusarov, V., Almjashev, V., Lopukh, D., Tromm, W., Bottomley, P., Fischer, M., Piluso, P., Miassoedov, A., Altstadt, E., Willschuetz, H., Fichot, F., 2006. Experimental Study of Interactions Between Suboxidized Corium and Reactor Vessel Steel, Proceedings of the International Congress on Advances in Nuclear Power Plants - Embedded International Topical Meeting at the 2006 ans Annual Meeting, Reno, NV USA, paper 6054. Dubyk, Y., Antonchenko, V., 2020. In-Vessel Core Melt Retention Strategy Applied for the Rivne VVER-440 Unit, Proceedings of the 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, Online. ASME, paper V001T01A018. https://doi.org/10.1115/ICONE2020-16913 International Atomic Energy Agency, 2008. Thermophysical Properties of Materials for Nuclear Engineering: A Tutorial and Collection of Data. IAEA, Vienna. International Atomic Energy Agency, 2020. Advances in Small Modular Reactor Technology Developments. IAEA, Vienna. Ma, W., Yuan, Y., Sehgal, B. R., 2016. In-vessel melt retention of pressurized water reactors: Historical review and future research needs. Engineering 2(1), 103-111. https://doi.org/10.1016/J.ENG.2016.01.019 Pivano, A., Piluso, P., Chikhi, N., Delacroix, J., Fouquart, P., Le Tellier, R., 2019. Experiments on interactions of molten steel with suboxidized corium crust for in-vessel melt retention. Nuclear Engineering and Design 355, paper 110271. https://doi.org/10.1016/j.nucengdes.2019.110271 Sasaki, R., Yamaji, A., Uchimura, K., 2023. Design study of small modular reactor class super fast reactor core for in-vessel retention. Journal of Nuclear Engineering and Radiation Science 9(2), paper 021501. https://doi.org/10.1115/1.4053827 Theofanous, T. G., Liu, C., Additon, S., Angelini, S., Kymäläinen, O., Salmassi, T. 1997. In -vessel coolability and retention of core melt. Nuclear Engineering and Design 169(1-3), 1-48. https://doi.org/10.1016/S0029-5493(97)00009-5