Abstract
The demand of accident tolerant fuel cladding materials provides a momentum for the development of FeCrAl alloys. To prove its potential, this work studied the corrosion behavior of FeCrAl alloys in H3BO3- and LiOH- containing water at 360 °C and 18.5 MPa for 500 h. XPS, XRD, SEM, Raman and AFM analyses were employed to identify oxide films, and the early corrosion mechanism of FeCrAl was discussed. Duplex oxide films were found on the surface of FeCrAl. The inner layer was Fe-Cr-Al spinel, and the outer crystals was dominantly composed of Fe2O3, accompanied by Fe3O4, FeCr2O4, NiFe2O4 and Li2Fe3O4. Similar to FeCrAl, Zircaloy-4 showed negligible weight change. However, its surface corrosion was more severe, and the oxides formed were mainly ZrO2 and Zr3O1-X. Li6Zr2O7 and other sub oxides were also observed.
| Original language | English |
|---|---|
| Article number | 153299 |
| Journal | Journal of Nuclear Materials |
| Volume | 557 |
| DOIs | |
| State | Published - 15 Dec 2021 |
Keywords
- Corrosion
- FeCrAl alloys
- Water environment
- Zircaloy-4
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