Authors
DJM King, AJ Knowles, D Bowden, MR Wenman, S Capp, M Gorley, J Shimwell, L Packer, MR Gilbert, A Harte
Publication date
2022/2/1
Source
Journal of Nuclear Materials
Volume
559
Pages
153431
Publisher
North-Holland
Description
This review considers current Zr alloys and opportunities for advanced zirconium alloys to meet the demands of a structural material in fusion reactors. Zr based materials in the breeder blanket offer the potential to increase the tritium breeding ratio above that of Fe, Si and V based materials. Current commercial Zr alloys might be considered as a material in water-cooled breeder blanket designs, due to the similar operating temperature to fission power plants. For breeder blankets designed to operate at higher temperatures, current commercial Zr alloys will not meet the high temperature strength and thermal creep requirements. Hence, Zr alloys with an operational temperature capability beyond that of current commercial fission alloys have been reviewed, specifically: binary Zr alloy systems Zr-Al, Zr-Be, Zr-Cr, Zr-Nb Zr-Ti, Zr-Si, Zr-Sn, Zr-V and Zr-W; as well as higher order Zr alloys Zr-Mo-Ti, Zr-Nb-Ti, Zr-Ti-Al-V and …
Total citations
20222023202461022
Scholar articles
DJM King, AJ Knowles, D Bowden, MR Wenman… - Journal of Nuclear Materials, 2022