Abstract
Two strategies were explored to improve the Pb-16Li compatibility of Fe-base alloys for a fusion energy blanket system. The use of thin (∼50 μm) Al-rich diffusion coatings on Grade 92 (9Cr-2W) substrates significantly reduced the mass loss in static Pb-Li capsule tests for up to 5000 h at 600 °C and 700 °C. However, significant Al loss was observed at 700 °C. Thicker coatings with Fe-Al intermetallic layers partially spalled after exposure at 700 °C, suggesting that coating strategies are limited to lower temperatures. To identify compositions for further alloy development, model FeCrAlY alloys with 10-20 wt.%Cr and 3-5%Al were exposed for 1000 h at 700 °C. There was little effect on mass change of varying the Cr content, however, alloys with <5% Al showed mass losses in these experiments. For both coatings and FeCrAl alloys, the surface reaction product was LiAlO2 after exposure and cleaning.
| Original language | English |
|---|---|
| Pages (from-to) | 330-334 |
| Number of pages | 5 |
| Journal | Journal of Nuclear Materials |
| Volume | 455 |
| Issue number | 1-3 |
| DOIs | |
| State | Published - Dec 2014 |
Funding
Research sponsored by the U.S. Department of Energy (DOE), Office of Fusion Energy Sciences, Fusion Energy Materials Program and Research supported by the Center for Nanophase Materials Sciences (CNMS), which is sponsored by the Scientific User Facilities Division, Office of Basic Energy Sciences, U.S. Department of Energy . T.M. Lowe, M.S. Stephens, T.S. Geer, T.L. Jordan, L.R. Walker, K. Perry and D.N. Leonard assisted with the experimental work. S.J. Pawel and D.T. Hoelzer provided comments on the results and manuscript.