Journal
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
Volume 20, Issue -, Pages 801-810Publisher
ELSEVIER
DOI: 10.1016/j.jmrt.2022.07.113
Keywords
Cu-base alloys; heat treatment; precipitation; microstructure characterization; fusion reactor technology
Funding
- Culham Centre for Fusion Energy (CCFE)
- EPSRC [EP/T012250/1]
- International Research Centre for Nuclear Materials Science of the Institute for Materials Research, Tohoku University
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During aging of Cu-0.55Cr-0.07Zr alloy at 480 degrees C, Cr-rich precipitates form initially, and with longer aging times, precipitates coarsen and transition from spherical to disc-like morphology. Zr segregation is also detected at the precipitate sites. At peak aging, precipitates reach an average size of about 9 nm. The presence of Zr atoms and the disc-like morphology of overaged precipitates should be considered in assessing their stability under irradiation and as potential sinks for lattice defects.
We have monitored the full-stage precipitate evolution in Cu-0.55Cr-0.07Zr alloy during aging at 480 degrees C (753 K) up to 14 days (20160 min), using micro-hardness, positron annihilation spectroscopy, electron microscopy and atom probe tomography. Cr-rich precipitates form during the early stages of aging, and after 5.5 min the distribution is characterised by a number density of 8x10(23) m(-3) and an average precipitate size of 2.5 nm. At that time, Zr segregation is also detected at the precipitate sites. Longer aging times lead to precipitate coarsening, simultaneously with the occurrence of a Zr-rich shell around precipitates potentially to help reduce local coherency strains. Peak aging of the alloy is attained after 120 min of aging, and overaging induces further precipitate coarsening and the transition from spherical to disc-like morphology. At the longest aging time of 14 days, the precipitates maintain a face-centred cubic symmetry, reaching an average size of similar to 9 nm at a density of 0.2 x10(22) m(-3). The presence of Zr atoms at the precipitate site and interface, and the disc-like morphology of overaged precipitates, should be considered when assessing the precipitate stability under irradiation and the precipitate/matrix interface as a potential sink for radiation-induced lattice defects. (C) 2022 The Author(s). Published by Elsevier B.V.
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