Abstract
In an attempt to explore the potential of oxide dispersion strengthened (ODS) ferritic steels for fission and fusion structural materials applications, a set of ODS steels with varying oxide particle dispersion were irradiated at 650°C, using 3.2 MeV Fe+ and 330 keV He+ ions simultaneously. The void formation mechanisms in these ODS steels were studied by juxtaposing the response of a 9Cr-2WVTa ferritic/martensitic steel and solution annealed AISI 316LN austenitic stainless steel under the same irradiation conditions. The results showed that void formation was suppressed progressively by introducing and retaining a higher dislocation density and finer precipitate particles. Theoretical analyses suggest that the delayed onset of void formation in ODS steels stems from the enhanced point defect recombination in the high density dislocation microstructure, lower dislocation bias due to oxide particle pinning, and a very fine dispersion of helium bubbles caused by trapping helium atoms at the particle-matrix interfaces.
| Original language | English |
|---|---|
| Pages (from-to) | 264-274 |
| Number of pages | 11 |
| Journal | Journal of Nuclear Materials |
| Volume | 280 |
| Issue number | 3 |
| DOIs | |
| State | Published - Aug 2000 |
Funding
This research was sponsored in part by the Division of Materials Sciences, US Department of Energy under contract No. DE-AC05-00OR22725 and in part by the Office of Fusion Energy, US Department of Energy, under contract No. W-7405-eng-26 with UT-Battelle, LLC. One of the authors, Kim, thanks ORNL for the support during his graduate research. The authors thank Drs Kleuh and Rowcliffe for technical review of the manuscript.
| Funders | Funder number |
|---|---|
| Office of Fusion Energy | |
| US Department of Energy | DE-AC05-00OR22725 |
| Division of Materials Sciences and Engineering |