Supercritical water-cooled reactor (SCWR) was chosen as Generation IV reactor concept in Canada to utilize Canada’s expertise and technical capabilities from past research and designs. The conceptual design of Canadian SCWR has a core outlet temperature of 650 C at 25 MPa and a peak cladding temperature as high as 800 C. Corrosion/oxidation resistance is an important factor in material selections and also coating considerations. Most of the reported supercritical water (SCW) test data have been obtained at temperatures up to 700 C as no autoclave exists that can operate above 700 C at supercritical pressures and temperatures. Superheated steam (SHS) is used as a surrogate fluid to SCW in this study to evaluate two coating materials, FeCrAlY and NiCrAl, at 800 C. The results showed that the FeCrAlY became discolored rapidly while NiCrAl still maintained some metallic sheen after 600 h. The weight change results suggest that more oxide formation took place on FeCrAlY than NiCrAl. In particular, grain boundary oxide (Al2O3) formed on FeCrAlY surface upon exposure to steam after 300 h. Further exposure caused more intragranular Al2O3 to form, in addition to magnetite formation on the grain boundary regions. For NiCrAl samples, NiO formed after steam exposure for 300 h. Spinel and (Cr,Al)2O3 were also found after 300 h along with very limited amount of Al2O3. After 600 h, Al2O3 became well developed on NiCrAl and the coverage of spinel and Cr2O3 on the surface reduced.

Additional Metadata
Keywords FeCrAlY, NiCrAl, SEM/EDS, Superheated steam, XRD
Persistent URL dx.doi.org/10.1115/1.4037668
Journal Journal of Nuclear Engineering and Radiation Science
Citation
Saez-Maderuelo, A. (Alberto), McTaggart, M. (Michael), Huang, X, & Maffiotte, C. (Cesar). (2018). Microstructure study of nicraly and fecraly exposed to superheated steam at 800 C. In Journal of Nuclear Engineering and Radiation Science (Vol. 4). doi:10.1115/1.4037668