| Article ID | Journal | Published Year | Pages | File Type |
|---|---|---|---|---|
| 1565637 | Journal of Nuclear Materials | 2013 | 7 Pages |
Abstract
⺠Zry-4, Zr-2.5Nb (PT) and Zr-1Nb were tested in steam and in LiOH solutions at high temperature. ⺠Oxide barrier layer may be present in Zr-Nb alloys even after 16 h in 1 M LiOH. ⺠In 1 M LiOH, the hydrogen uptake of Zr-Nb alloys is lower than that of Zry-4. ⺠The β-Zr phase amount in Zr-1Nb improves the oxide thickness and hydrogen uptake.
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Authors
S. Müller, L. Lanzani,