Abstract
A FeCrAl substrate was pre-oxidized for 2 h at 1000 °C to thermally grow an external Al2O3 scale and then isothermally exposed to Pb-17 at.% Li for 1000 h at 800 °C to determine if this layer would protect the underlying alloy from dissolution. After exposure, a small mass gain was measured, indicating that the layer did inhibit dissolution. However, characterization of the external layer determined that it had transformed to LiAlO2 with an increased thickness and a much larger grain size than the original layer. This observation has implications for the use of Al2O3 as a permeation barrier in Pb-Li cooled fusion blanket systems.
Original language | English |
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Pages (from-to) | 108-113 |
Number of pages | 6 |
Journal | Journal of Nuclear Materials |
Volume | 376 |
Issue number | 1 |
DOIs | |
State | Published - May 15 2008 |
Funding
The research was sponsored by the US Department of Energy (DOE), Office of Fusion Energy Sciences, Fusion Energy Materials Program, under Contract DE-AC05-00OR22725 with UT-Battelle, LLC. D.F. Wilson and J.R. DiStefano consulted on the experimental procedure. J.L. Moser, K.S. Reeves, T. Brummett and D. Coffey assisted with the experimental work. D. Hoelzer and J.R. DiStefano provided comments on the manuscript.
Funders | Funder number |
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Fusion Energy Materials Program | DE-AC05-00OR22725 |
U.S. Department of Energy | |
Fusion Energy Sciences |