|About this Abstract
||2021 TMS Annual Meeting & Exhibition
||Corrosion in Heavy Liquid Metals for Energy Systems
||Preliminary Results on the Compatibility of Fe-Cr-Al and
Fe-Cr-Al-Mo Steels with Liquid Sodium at 700 °C.
||Marie Romedenne, Rishi Pillai, Bruce Pint
|On-Site Speaker (Planned)
Continued interest exists in the development of sodium fast nuclear reactors, which are able to achieve higher operating temperatures (up to 700 °C) than light water reactors and promise a 60 year design life. As new materials are developed for other applications, their behavior in liquid sodium has not been explored. The corrosion behavior and post-exposure tensile properties of oxide dispersion strengthened FeCr, FeCrAl and FeCrAlMo steels were evaluated after 1,000 h exposures at 700 °C in commercially-sourced sodium with and without Zr foil to getter oxygen. The presence of oxygen in the liquid sodium led to the formation of NaCrO2 and AlNaO2 oxide scale which resulted, in some cases, to the formation of intermetallic phases in the underlying alloy. While NaCrO2 formation was observed to be detrimental to the tensile properties after exposure, further investigation is needed to evaluate the long-term effect of AlNaO2.