About this Abstract |
Meeting |
2021 TMS Annual Meeting & Exhibition
|
Symposium
|
Accelerated Discovery and Qualification of Nuclear Materials for Energy Applications
|
Presentation Title |
Development of Sintered High Strength and Thermal Conductivity Cu-Cr-Nb-Zr Alloy for Fusion Components |
Author(s) |
Bin Cheng, Ling Wang, David Sprouster, Jason Trelewicz, Weicheng Zhong, Ying Yang, Steven Zinkle, Lance Snead |
On-Site Speaker (Planned) |
Bin Cheng |
Abstract Scope |
High-strength, high-thermal conductivity, and creep-resistant Cu-Cr-Nb-Zr alloys have attracted significant interests for the application in fusion energy system as the substrate materials for plasma-facing components. In this work, a Cu-Cr-Nb-Zr alloy was fabricated using direct current sintering (spark plasma sintering) from a gas atomized feedstock powder. The microstructure of sintered Cu-Cr-Nb-Zr alloy were characterized by synchrotron X-ray diffraction, small-angle X-ray scattering, scanning electron microscopy, and transmission electron microscopy. A high-thermal and electrical conductivity were achieved on the sintered CCNZ alloy together with a high hardness. A multi-modal precipitate distribution is achieved via our approach, with both coarse Cr and medium-sized Cr2Nb precipitates located at grain boundaries, and a high-density of nano-scale Cr precipitates evenly distributed throughout the Cu matrix. Based on the quantified microstructure evolution, we outline a possible precipitation scheme, which demonstrates the role of high-sintering pressure and recrystallization in facilitating grain boundary pinning precipitates. |
Proceedings Inclusion? |
Planned: |
Keywords |
Nuclear Materials, Copper / Nickel / Cobalt, Extraction and Processing |