Enhanced Mechanical Properties and Wear Resistance of FeCrAl Alloys at ~ 300°C and Higher Temperatures

Journal Article · 23 April 2024 · JOM. Journal of the Minerals, Metals & Materials Society

DOI: https://doi.org/10.1007/s11837-024-06540-3 · OSTI ID:2340208

Dolley, Evan J.; Zhang, Wanming; Zorn, Gilad; Sand, Tommy; Rebak, Raul B.

Abstract Worldwide, light water reactors (LWRs) have been using zirconium (Zr)-based alloys for the cladding of the uranium dioxide fuel for more than 6 decades. Zr alloys oxidize rapidly in the presence of water and steam at temperatures > 450°C; therefore, they do not respond well to scenarios of loss of coolant accidents. There is a global effort by nuclear materials technologists to find more robust or stronger cladding materials for LWRs. One option is to use an iron-chromium-aluminum (FeCrAl) alloy since they have excellent resistance to high temperature oxidation and superior mechanical properties at LWR operation temperatures. Results show that (1) FeCrAl alloys have better mechanical properties than Zr alloy and are orders of magnitude more resistant to creep at temperatures higher than LWR normal operation conditions. (2) FeCrAl alloys have better resistance to fretting wear than Zr alloys at the normal operation conditions of LWRs.

• Sponsoring Organization: USDOE Office of Nuclear Energy (NE), Nuclear Fuel Cycle and Supply Chain
• Grant/Contract Number: NE0009047
• OSTI ID: 2340208
• Journal Information: JOM. Journal of the Minerals, Metals & Materials Society, Journal Name: JOM. Journal of the Minerals, Metals & Materials Society; ISSN 1047-4838
• Publisher: Springer Science + Business MediaCopyright Statement
• Country of Publication: United States
• Language: English