Abstract
High-strength, high-conductivity copper alloys are suitable heat-sink materials for the divertor of magnetically confined fusion reactors subject to high thermal loads. Tensile specimens of a commercial high-strength Cu, Cr, Zr alloy were irradiated in the HFR reactor in Petten at 150 and 250°C. The total accumulated damage (10 dpa) and the damage production rate (3.3 × 10 −7 dpa/ s) correspond to the envisaged operating requirements of the ITER divertor. Tensile testing after irradiation was performed in the LMA hot laboratory at JRC Ispra, at a single constant strain rate of 2.9 × 10 −4/ s. At 155°C an increase of yield strength (YS) was measured and a decrease of uniform elongation (UE) from 5% to virtually zero. Persisting high total elongation (TE) values of about 9% indicate that the ductile fracture mode is not affected. Irradiation hardening at 255°C is less pronounced. In the light of this study and of published results, the temperature of 275°C is proposed as a conservative temperature limit for use of fully precipitation hardened Cu-Cr-Zr (Mg) alloys to exclude irradiation softening.
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