Abstract
Pre- and post-deformation microstructures and tensile properties of the newly-developed oxide dispersion strengthened (ODS) ferritic steels, K1 (Fe-19Cr-0.3W-0.3Ti-0.3Y2O3) and K4 (Fe-19Cr-4Al-2W-0.3Ti-0.3Y2O3) for nuclear fusion reactors and Generation IV nuclear fission systems were investigated. The nano-oxides of the K1 were cubic pyrochlore Y2Ti2O7, while those of K4 were mainly perovskite AlYO3, which was confirmed by transmission electron microscopy and X-ray diffraction (XRD) analyses. K1 was found to have much higher strength than K4 and the difference in the nano-oxides of K1 and K4 can account for this difference. Most of the extracted residues in the K1 and K4 identified by XRD consisted of M23C6 carbides.
Original language | English |
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Pages (from-to) | 222-228 |
Number of pages | 7 |
Journal | Journal of Nuclear Materials |
Volume | 367-370 A |
Issue number | SPEC. ISS. |
DOIs | |
Publication status | Published - 2007 Aug 1 |
Externally published | Yes |
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Materials Science(all)
- Nuclear Energy and Engineering