Material Challenges for Corrosive Environments and High Temperatures in Lead-Cooled Fast Reactor
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Abstract
Research on one of the generation IV reactors, the Lead-Cooled Fast Reactor (LFR), began in the 1950s. The development of this reactor continues until now. However, there are material challenges in the development of LFR. LFR coolant that uses liquid Pb or Pb-Bi is one of the challenges in this reactor because it causes severe corrosion. Researchers have tested various materials such as steel, ceramics, composites, and refractory alloys in liquid Pb or Pb-Bi environments to assess their corrosion resistance. These materials have shown improved radiation performance at high temperatures and have been developed (such as ODS, FeCrAl, SS316, AISI 316 EP823, AISI 304, and HCM12A). However, these materials are not yet sufficiently compatible with corrosion performance. The results indicate that no metal or ceramic material currently proves to be completely resistant to corrosion and radiation over the long term. The LFR system is intriguing but has limited applicability until suitable construction material designs are further identified.
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Janah, Y., Angelina, T., & Mustari, A. (2025). Material Challenges for Corrosive Environments and High Temperatures in Lead-Cooled Fast Reactor. Indonesian Journal of Physics, 35(2), 17 - 25. https://doi.org/10.5614/itb.ijp.2024.35.2.3
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References
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Alessandro Alemberti, Guido Renda, Giacomo G.M. Cojazzi, Andrei Moiseev, Craig Smith, Kamil Tucek, & Giacomo Grasso. (2020). GIF LEAD-COOLED FAST REACTOR PROLIFERATION RESISTANCE AND PHYSICAL PROTECTION WHITE PAPER Proliferation Resistance and Physical Protection Working Group (PRPPWG) Lead-Cooled Fast Reactor Provisional System Steering Committee (LFR pSSC). April.
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Allen, T. R., & Crawford, D. C. (2007b). Lead-Cooled Fast Reactor Systems and the Fuels and Materials Challenges. Science and Technology of Nuclear Installations, 2007(December 2007), 1–11. https://doi.org/10.1155/2007/97486
Barbier, F., Benamati, G., Fazio, C., & Rusanov, A. (2001). Compatibility tests of steels in flowing liquid lead–bismuth. Journal of Nuclear Materials, 295(2-3), 149-156.
Cinotti, L., Smith, C. F., Artioli, C., Grasso, G., & Corsini, G. (2010). Lead-Cooled Fast Reactor (LFR) Design: Safety, Neutronics, Thermal Hydraulics, Structural Mechanics, Fuel, Core, and Plant Design. Handbook of Nuclear Engineering, 2749–2840. https://doi.org/10.1007/978-0-387-98149-9_23
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Dömstedt, P., Lundberg, M., & Szakalos, P. (2019). Corrosion studies of low-alloyed FeCrAl steels in liquid lead at 750° C. Oxidation of Metals, 91, 511-524.
Ejenstam, J., Halvarsson, M., Weidow, J., Jönsson, B., & Szakalos, P. (2013). Oxidation studies of Fe10CrAl–RE alloys exposed to Pb at 550 C for 10,000 h. Journal of Nuclear Materials, 443(1-3), 161-170.
Fazio, C., Ricapito, I., Scaddozzo, G., & Benamati, G. (2003). Corrosion behaviour of steels and refractory metals and tensile features of steels exposed to flowing PbBi in the LECOR loop. Journal of nuclear materials, 318, 325-332.
Grasso, G., Petrovich, C., Mattioli, D., Artioli, C., Sciora, P., Gugiu, D., Bandini, G., Bubelis, E., & Mikityuk, K. (2014). The core design of ALFRED, a demonstrator for the European lead-cooled reactors. Nuclear Engineering and Design, 278, 287–301. https://doi.org/10.1016/j.nucengdes.2014.07.032
Hejzlar, P., Buongiorno, J., Macdonald, P. E., & Todreas, N. E. (2004). Design Strategy and Constraints for Medium-Power Lead-Alloy- Cooled Actinide Burners. Nuclear Technology, 147(3), 321–343. https://doi.org/10.13182/NT147-321
IAEA. (2012). Status of Fast Reactor Research.
IAEA. (2019). Waste from Innovative Types of Reactors and Fuel Cycles. IAEA Nuclear Energy Series, No. NW-T-1, 1–132.
Klueh, R. L., & Harries, D. R. (2001, January). High-chromium ferritic and martensitic steels for nuclear applications. West Conshohocken, PA: AsTM.
Kurata, Y., & Futakawa, M. (2004). Excellent corrosion resistance of 18Cr–20Ni–5Si steel in liquid Pb–Bi. Journal of Nuclear Materials, 325(2-3), 217-222.
Loewen, E. P., & Tokuhiro, A. T. (2003). Status of research and development of the lead-alloy-cooled fast reactor. Journal of Nuclear science and technology, 40(8), 614-627.
Macdonald, P. E., & Buongiorno, J. (2002). Lead or Lead-Bismuth Cooled Reactor That Produces Low. Plant Engineering, October.
Machut, M., Sridharan, K., Li, N., Ukai, S., & Allen, T. (2007). Time dependence of corrosion in steels for use in lead-alloy cooled reactors. Journal of nuclear materials, 371(1-3), 134-144.
Maulana, A. (2023). Studi korosi baja dalam reaktor nuklir berpendingin Pb-Bi cair menggunakan metode dinamika molekular (Disrtasi S3). Institut Teknologi Bandung, Bandung, Indonesia.
Nakazima, T., Rivai, A. K., Hata, K., Dostal, V., & Takahashi, M. (2006). Study plan for material corrosion test in lead and bismuth eutectic at high temperature. International Conference on Nuclear Engineering, Proceedings, ICONE, 2006, 1–3. https://doi.org/10.1115/ICONE14-89420
NEA. (2015). Handbook on Lead-bismuth Eutectic Alloy and Lead Properties , Materials Compatibility , Thermal- hydraulics and Technologies. Nuclear Science, 647–730.
Orlov, V. V., Filin, A. I., Lopatkin, A. V., Glazov, A. G., Sukhanov, L. P., Volk, V. I., Poluektov, P. P., Ustinov, O. A., Vorontsov, M. T., Leontiev, V. F., & Karimov, R. S. (2005). The closed on-site fuel cycle of the BREST reactors. Progress in Nuclear Energy, 47(1–4), 171–177. https://doi.org/10.1016/j.pnucene.2005.05.017
Pramono, Y., Takahashi, M., Sofue, H., Matsumoto, M., & Huang, F. (2005). 7 MPa Commissioning of Two-phase Flow Loop for Pb-Bi Cooled Direct Contact Boiling Water Small Fast Reactor. 16(1), 7–12.
Qi, Y., & Takahashi, M. (2003). ICONE11-36375 STUDY ON CORROSION PHENOMENA OF STEELS IN PB-BI FLOW. In The Proceedings of the International Conference on Nuclear Engineering (ICONE) 2003 (p. 39). The Japan Society of Mechanical Engineers.
Rivai, A. K., & Takahashi, M. (2010). Corrosion characteristics of materials in Pb–Bi under transient temperature conditions. Journal of nuclear materials, 398(1-3), 139-145.
Runge, J. M., Leibowitz, L., Barnes, L. A., Raraz, A. G., & McDeavitt, S. M. (2003). Performance of structural materials in lead-based reactor coolants at temperatures up to 800 {degrees} C (No. ANL/CMT/CP-111509). Argonne National Lab.(ANL), Argonne, IL (United States).
Sekimoto, H. (2010). Light a CANDLE An Innovative Burnup Strategy of Nuclear Reactors.
Sofu, T. (2019). Overview of Lead-Cooled Fast Reactor (LFR) Technology.
Wang, H., Qiu, X., Li, Y., Liu, B., Li, W., Su, D., & Tang, Z. (2024). Short-term corrosion behavior and mechanism of 316 stainless steel in liquid Pb at 650 and 750° C. Journal of Materials Engineering and Performance, 33(14), 7210-7221.
Wang, W., Yang, C., You, Y., & Yin, H. (2023). A Review of Corrosion Behavior of Structural Steel in Liquid Lead–Bismuth Eutectic. Crystals, 13(6), 968. https://doi.org/10.3390/cryst13060968
Wu, C., Dasika, K. K., Chen, Y., & Moujaes, S. (2002). Numerical Modeling of Lead Oxidation in Controlled Lead Bismuth Eutectic Systems: Chemical Kinetics and Hydrodynamic Effects. International on Advanced Nuclear Power Plants in Hollywood, Florida, June 9e13.
Yamashita, S., Oka, K., Ohnuki, S., Akasaka, N., & Ukai, S. (2002). Phase stability of oxide dispersion-strengthened ferritic steels in neutron irradiation. Journal of nuclear materials, 307, 283-288.
Zhang, Y., Wang, C., Lan, Z., Wei, S., Chen, R., Tian, W., & Su, G. (2020). Review of Thermal-Hydraulic Issues and Studies of Lead-based fast reactors. Renewable and Sustainable Energy Reviews, 120(December 2019). https://doi.org/10.1016/j.rser.2019.109625
Zrodnikov, A. V., Toshinsky, G. I., Komlev, O. G., Dragunov, Y. G., Stepanov, V. S., Klimov, N. N., Kopytov, I. I., & Krushelnitsky, V. N. (2006). Nuclear power development in market conditions with use of multi-purpose modular fast reactors SVBR-75/100. Nuclear Engineering and Design, 236(14–16), 1490–1502. https://doi.org/10.1016/j.nucengdes.2006.04.005