High temperature zirconium alloys for fusion energy

This review considers current Zr alloys and opportunities for advanced zirconium to meet the demands of a structural material in fusion reactors. based materials breeder blanket offer potential increase tritium breeding ratio above that Fe, Si V materials. Current commercial might be considered as water-cooled designs, due similar operating temperature fission power plants. For blankets designed operate at higher temperatures, will not high strength thermal creep requirements. Hence, with an operational capability beyond have been reviewed, specifically: binary alloy systems Zr-Al, Zr-Be, Zr-Cr, Zr-Nb Zr-Ti, Zr-Si, Zr-Sn, Zr-V Zr-W; well order Zr-Mo-Ti, Zr-Nb-Ti, Zr-Ti-Al-V Zr-Mo-Sn. It is concluded that, further work, could achieve required strength, alongside ductility, while maintaining low neutron cross-section. However, there limited data uncertainty regarding performance microstructural stability majority temperatures 500–700 °C, which they would expected helium- liquid metal-cooled designs.