PSI - Issue 59

Anatolii Klymenko et al. / Procedia Structural Integrity 59 (2024) 214–221 Anatolii Klymenko et al. / Structural Integrity Procedia 00 (2019) 000 – 000

221

8

chemical elements over the structure after testing does not depend on the exposure time and is similar for both 450 and 650 °C. 4. Conclusions 1. According to the results of corrosion tests, it was found that the dynamics of change in the corrosion rate of stainless steel AISI 316L is characterized by a tendency to increase the index by ~5 times with an increase in temperature from 450 °C to 650 °C, as well as a decrease in the index value by ~4.5 times at the melt temperature of 450 °C and ~1.3 times at the melt temperature of 650 °C with an increase in test duration from 240 to 1440 h, respectively, due to the formation of a protective dense oxide film. 2. The corrosion process is accompanied by etching of grain boundaries with penetration of lead from the melt into the base metal matrix with simultaneous selective dissolution of alloying elements (Cr, Ni, Mn) already after 240 h of exposure. 3. Increasing the test temperature from 450 to 650 °C leads to an increase in the oxygen concentration in the oxidized layer from 10.56 wt.% to ~70 wt.%, as well as to the formation of corrosion products in the form of a multilayer structure with a clear separation and sequential alternation of layers based on lead and lead-iron already after 240 hours of testing. 4. The distribution of chemical elements over the structure does not depend on the exposure time in the lead melt and is the same for both 450 °C and 650 °C. Reference Benamati, G., Fazio, C., Piankova, H., Rusanov, A., 2002. Temperature effect on the corrosion mechanism of austenitic and martensitic steels in lead-bismuth. Journal of Nuclear Materials 301, 23 – 27. Cionea, С., Abad, M.D., Aussat, Y., Frazer, D. , Gubser, A.J., Hosemann, P., 2016. Oxide scale formation on 316L and FeCrAl steels exposed to oxygen controlled static LBE at temperatures up to 800 °C. Solar Energy Materials and Solar Cells 144, 235 – 246. Fedirko, V., Kukhar, I., Mel’nyk, K., 2019. Influ ence of the structural-phase state of chromium steels on their corrosion in lead melts. Material Science, 54, 551 – 555. Gromov, B., Belomitcev, Yu., Yefimov, E., Leonchuk, M., Martinov, P., Orlov, Yu., Pankratov, D., Pashkin, Yu., Toshinsky, G., Chekunov, V., Shmatko, B., Stepanov, V., 1997. Use of lead-bismuth coolant in nuclear reactors and accelerator-driven systems. Nuclear Engineering and Design 173, 207 – 217. Huang, X., Pang, B., Zhou, X., Yin, Y., 2021. Experimental Investigation on the Cleaning Effect and Influence Rule of Hydrogen Peroxide – Acetic Acid on Lead – Bismuth Eutectic Alloy. Frontiers in Energy Research 9, 735199. Klymenko, A., Kovalenko, S., Polishko, H., Tunik, A., Byk, M., Buket, O., Shapiro, O., 2022. Corrosion resistance of stainless steel AISI 310s in lead melt at the temperature 450 °C. Material Science, 58, 591 – 596 Rozumová, L., Košek, L., Vít, J., Hojná, A., Halodová, P., 2021. Comparison of Corrosion Behavior of the Austenitic Stainless Steel 316 L in Static and Flowing Liquid Lead. Journal of Nuclear Engineering and Radiation Science 7(2), 021605. Schroer, C., Wedemeyer, O., Novotny, J., Skrypnik, A., Konys, J., 2014. Selective leaching of nickel and chromium from Type 316 austenitic steel in oxygen-containing lead-bismuth eutectic (LBE). Corrosion Science 84, 113 – 124. Toshinsky, G., Dedul, A., Komlev, O., Kondaurov, A., Petrochenko, V., 2020. Lead – bismuth and lead as coolants for fast reactors. World Journal of Nuclear Science and Technology 10, 65 – 75. Tsisar, V., Schroer, C., Wedemeyer, O., Skrypnik, A., Konys, J., 2014. Corrosion behavior of austenitic steels 1.4970, 316L and 1.4571 in flowing LBE at 450 and 550 °C with 10 − 7 mass% dissolved oxygen. Journal of Nuclear Materials 454, 332 – 342. Tsisar, V., Schroer, C., Wedemeyer, O., Skrypnik, A., Konys, J., 2016. Long- term corrosion of austenitic steels in flowing LBE at 400 °C and 10- 7 mass% dissolved oxygen in comparison with 450 and 550 °C. Journal of Nuclear Materials 468, 305 – 312. Wang, H., Liang, G., Meng, C., An, X., Wang, Y., He, X., 2023. A comparative study on the corrosion performance of four FeCrAl alloys with different Cr contents in contact with oxygen-saturated LBE. Journal of Materials Research and Technology 23, 3492 – 3504. Wang, R., Xi, Q., Shixin, G., Weihua, L., Wenjie, L., Yuanming, L., Zhongfeng, T., 2022. Corrosion behavior of 316 stainless steel arc parts in liquid lead at 650 °C under high oxygen concentrations. RSC Advances 12, 32700 – 32707. Yas’kiv, O., Fedirko, V., Kukhar, I., 2016. The effect of the struc tural state of steels on the mechanical properties in the oxygen saturated lead. Problems of Atomic Science and Technology 2(102), 32 – 36. Yeliseyeva, O., Tsisar, V., Benamati, G., 2008. Influence of temperature on the interaction mode of T91 and AISI 316L steels with Pb-Bi melt saturated by oxygen. Corrosion Science 50, 1672 – 1683.