About this Abstract |
| Meeting |
2026 TMS Annual Meeting & Exhibition
|
| Symposium
|
Developments in Advanced Nuclear Structural Materials
|
| Presentation Title |
Microstructure, Electrical Resistivity, and Tensile Properties of Pristine and Neutron-Irradiated Bimodally Strengthened Cu Alloys |
| Author(s) |
Alice E. Perrin, Dai Hamaguchi, Josina W. Geringer, Yajie Zhao, Xiang Chen, Steve Skutnik, Jon D Poplawsky, Steve Zinkle, Yutai Katoh, Ying Yang |
| On-Site Speaker (Planned) |
Alice E. Perrin |
| Abstract Scope |
High strength, high conductivity copper alloys that can resist creep at high temperatures are the primary candidate materials for efficient heat exchangers in fusion reactors. High purity Cu–Cr–Nb–Zr (CCNZ-HP) alloys were designed to improve the strength and creep life of ITER Cu–Cr–Zr (CCZ) reference alloys through a bimodal distribution of strengthening phases. CCNZ-HP alloys have been found to have comparable electrical conductivity and tensile properties to CCZ alloys while demonstrating a substantially longer creep rupture life at 500 °C. We present characterization of the room temperature mechanical and electrical properties of neutron-irradiated CCNZ-HP and ITER grade CCZ alloys. The design and non-irradiated properties of two second generation alloys, CCNZ-HZ (“High Zr” Cu-Cr-Nb-Zr) and HCCZ (“High Cr” Cu-Cr-Zr), will be presented as well, and insights into the expected mechanical and thermal behavior after irradiation will be discussed in the context of the irradiated CCNZ-HP properties. |
| Proceedings Inclusion? |
Planned: |
| Keywords |
Copper / Nickel / Cobalt, Nuclear Materials, Mechanical Properties |