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Specification of CuCrZr Alloy Properties after Various Thermo-Mechanical Treatments and Design Allowables including Neutron I...

by Vladimir Barabash, G. Kalinin, Sergei Fabritsiev, Steven J Zinkle
Publication Type
Conference Paper
Journal Name
Journal of Nuclear Materials
Publication Date
Page Numbers
904 to 907
Volume
417
Issue
1-3
Conference Name
14th International Conference on Fusion Reactor Materials
Conference Location
Sapporo, Japan
Conference Date
-

Precipitation hardened CuCrZr alloy is a promising heat sink and functional material for various applica- tions in ITER, for example the first wall, blanket electrical attachment, divertor, and heating systems. Three types of thermo-mechanical treatment were identified as most promising for the various applica- tions in ITER: solution annealing, cold working and ageing; solution annealing and ageing; solution annealing and ageing at non-optimal condition due to specific manufacturing processes for engineer- ing-scale components. The available data for these three types of treatments were assessed and mini- mum tensile properties were determined based on recommendation of Structural Design Criteria for the ITER In-vessel Components. The available data for these heat treatments were analyzed for assess- ment of neutron irradiation effect. Using the definitions of the ITER Structural Design Criteria the design allowable stress intensity values are proposed for CuCrZr alloy after various heat treatments.