In the past few years, significant progress has been made in materials selection for Gen-IV SCWR fuel cladding applications. Current studies indicate that austenite stainless steels such as 310H are promising candidates for in-core applications. Alloys in this group are promising for their corrosion resistance, SCC resistance, high temperature mechanical properties and creep resistance at temperatures up to 700 °C. However, one under-studied area of this alloy is the long-term microstructure stability under the proposed reactor operating condition. Unstable microstructure not only results in embrittlement but also has the potential to reduce their resistance to corrosion or stress-corrosion cracking. In this study, stainless steels 310H and 304H were tested for their SCWR corrosion resistance and microstructure stability.
Li, J., Zheng, W., Penttilä, S., Liu, P., Woo, O. T., & Guzonas, D. (2014). Microstructure stability of candidate stainless steels for Gen-IV SCWR fuel cladding application. Journal of Nuclear Materials, 454(1-3), 7-11. https://doi.org/10.1016/j.jnucmat.2014.06.043