Abstract
Low-Cr oxide dispersion strengthened (ODS) FeCrAl alloys were developed as accident tolerant fuel cladding because of their excellent oxidation resistance at very high temperature, high strength and improved radiation tolerance. Fe-12Cr-5Al wt.% gas atomized powder was ball milled with Y2O3+FeO, Y2O3+ZrO2 or Y2O3+TiO2, and the resulting powders were extruded at 950 °C. The resulting fine grain structure, particularly for the Ti and Zr containing alloys, led to very high strength but limited ductility. Comparison with variants of commercial PM2000 (Fe-20Cr-5Al) highlighted the significant impact of the powder consolidation step on the alloy grain size and, therefore, on the alloy mechanical properties at T < 500 °C. These low-Cr compositions exhibited good oxidation resistance at 1400 °C in air and steam for 4 h but could not form a protective alumina scale at 1450 °C, similar to observations for fine grained PM2000 alloys. The effect of alloy grain size, Zr and Ti additions, and impurities on the alloy mechanical and oxidation behaviors are discussed.
| Original language | English |
|---|---|
| Pages (from-to) | 59-71 |
| Number of pages | 13 |
| Journal | Journal of Nuclear Materials |
| Volume | 501 |
| DOIs | |
| State | Published - Apr 1 2018 |
Funding
The authors would like to thank J. Turan, M. Howell, T Jordan, T. Lowe, C. Stevens, D. Harper, G. Cox for their help with the experimental work. They want also to acknowledge M.P. Brady and K. Field for reviewing the manuscript, and Kurt Terrani for his advice and guidance. This research was funded by the U.S. Department of Energy's Office of Nuclear Energy , Advanced Fuel Campaign . The FEI Talos F200X STEM was used as part of the Nuclear Science User Facility .