Abstract
The corrosion behavior and tensile properties of oxide dispersion strengthened (ODS) FeCr, FeCrAl, FeCrAlMo steels and 316H stainless steel were evaluated after 1000 h at 700 ∘C in static sodium with and without an oxygen getter (Zr foil). Without Zr foil to getter the dissolved oxygen in the liquid sodium, combined oxidation (formation of Cr, Fe-rich or Al-rich oxides) and dissolution of the studied materials was observed. For the ODS FeCr, Cr- and Fe-rich oxide formation and dissolution induced Cr depletion in the underlying alloy and led to the formation of laves phases that were observed to be detrimental to the room temperature tensile properties. For ODS FeCrAlMo and FeCrAl Al-rich oxide formation and dissolution resulted in Al depletion in the underlying alloys but did not impact tensile properties at room temperature. For 316H temperature induced sensitization combined with oxidation decreased room temperature tensile properties. With Zr foil added as oxygen getter, roughened surfaces and Al depletion profiles suggested the dissolution of ODS FeCr and FeCrAl into the liquid sodium while limited dissolution was observed for ODS FeCrAlMo and 316H. For the 316H and ODS FeCrAlMo steels, precipitates were formed at the grain boundaries after exposure. Tensile properties of ODS FeCr, FeCrAl and FeCrAlMo were not affected by the 1000 h corrosion exposure with Zr foil added to the sodium but for 316H temperature-induced grain boundary sensitization negatively affected the tensile properties.
| Original language | English |
|---|---|
| Article number | 153919 |
| Journal | Journal of Nuclear Materials |
| Volume | 569 |
| DOIs | |
| State | Published - Oct 2022 |
Funding
The authors would like to thank C. Massey for providing the ODS materials. T. Lowe, V. Cox, T. Geer, M. Stephens, A. Willoughby, K. Hedrick, E. Cakmak and M. Lance are thanked for their assistance with the experimental work. P. Tortorelli and J. Jun are acknowledged for their comments on the manuscript. This research was sponsored by the U.S. Nuclear Regulatory Commission. This manuscript has been authored by UT-Battelle, LLC under Contract no. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan ( http://energy.gov/downloads/doe-public-access-plan ). The authors would like to thank C. Massey for providing the ODS materials. T. Lowe, V. Cox, T. Geer, M. Stephens, A. Willoughby, K. Hedrick, E. Cakmak and M. Lance are thanked for their assistance with the experimental work. P. Tortorelli and J. Jun are acknowledged for their comments on the manuscript. This research was sponsored by the U.S. Nuclear Regulatory Commission. This manuscript has been authored by UT-Battelle, LLC under Contract no. DE-AC05-00OR22725 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a non-exclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The Department of Energy will provide public access to these results of federally sponsored research in accordance with the DOE Public Access Plan (http://energy.gov/downloads/doe-public-access-plan).
| Funders | Funder number |
|---|---|
| DOE Public Access Plan | |
| United States Government | |
| U.S. Department of Energy | |
| U.S. Nuclear Regulatory Commission | DE-AC05-00OR22725 |
Keywords
- Corrosion
- Oxide dispersion strengthened steels
- Sodium fast reactor