Article ID Journal Published Year Pages File Type
1568625 Journal of Nuclear Materials 2008 6 Pages PDF
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.

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Physical Sciences and Engineering Energy Nuclear Energy and Engineering
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