About this Abstract |
Meeting |
2023 TMS Annual Meeting & Exhibition
|
Symposium
|
Mechanical Behavior of Nuclear Reactor Materials and Components III
|
Presentation Title |
ODS Cu Materials for Fusion Application Produced by Mechanical Alloying |
Author(s) |
Carsten Bonnekoh, Andrei Galatanu, David Bürger, Thomas Gietzelt, Michael Rieth |
On-Site Speaker (Planned) |
Carsten Bonnekoh |
Abstract Scope |
Under the exposure to fusion neutrons, the current baseline copper alloy for the divertor heatsink (CuCrZr) suffers a loss of microstructural stability drastically lowering the bearable material temperature. Applying oxide-dispersion strengthened (ODS) Cu alloys is a promising attempt to overcome this dilemma. For this study, ODS Cu alloys were industrially produced using mechanical alloying (MA), which significantly differentiates these alloys from ODS Cu materials prepared by the internal oxidation method (better known under the trademark Glidcop). Here, we show the influence of alloy composition and alterations in parameters of MA on yield strength and toughness. Improvements in yield strength are considered with regard to changes in thermal conductivity. Preliminary results indicate that well-designed solid solution hardening in addition to ODS hardening is beneficial for the aggregated material performance. All results are discussed in the context of data for Cu1Cr0.1Zr and Glidcop Al-60 also acquired within this study for optimum comparability. |
Proceedings Inclusion? |
Planned: |
Keywords |
Copper / Nickel / Cobalt, Powder Materials, Mechanical Properties |