Full-stage precipitation during aging of Cu-0.55Cr-0.07Zr alloy for high heat flux fusion reactor technology

J. Hughes*, T. Toyama, M. Gorley, E. Jimenez-Melero*

*Corresponding author for this work

Research output: Contribution to journalArticlepeer-review

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Abstract

We have monitored the full-stage precipitate evolution in Cu-0.55Cr-0.07Zr alloy during aging at 480 °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 8×1023 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 ∼9 nm at a density of 0.2×1022 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.

Original languageEnglish
Pages (from-to)801-810
Number of pages10
JournalJournal of Materials Research and Technology
Volume20
Early online date1 Aug 2022
DOIs
Publication statusPublished - Sept 2022

Bibliographical note

Funding Information:
The authors of this work acknowledge the support of Culham Centre for Fusion Energy ( CCFE ). Mike Gorley would like to acknowledge funding from the EPSRC Grant EP/T012250/1. We also thank the International Research Centre for Nuclear Materials Science of the Institute for Materials Research, Tohoku University, for their financial travel support, as well as access to equipment and assistance in carrying out PAS and 3D-AP experiments.

Publisher Copyright:
© 2022 The Author(s).

Keywords

  • Cu-base alloys
  • fusion reactor technology
  • heat treatment
  • microstructure characterization
  • precipitation

ASJC Scopus subject areas

  • Ceramics and Composites
  • Biomaterials
  • Surfaces, Coatings and Films
  • Metals and Alloys

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