The precipitate microstructure of prime aged CuCrZr was coarsened by overaging to see if the larger precipitates could prevent the initiation of plastic flow localization in irradiated CuCrZr. A number of tensile and fracture toughness specimens of prime aged CuCrZr alloy were given overaging treatments at 873 K for 1, 2 and 4 h. A subset of these specimens were irradiated with fission neutrons in the BR-2 reactor at Mol (Belgium) at 333 K and 573 K to a dose level of ∼0.3 dpa. Both unirradiated and irradiated tensile specimens were tested at 295 K, 333 K and 573 K. Fracture toughness tests were carried out at 293, 333 and 573 K. Transmission electron microscopy was used to investigate the effects of overaging, subsequent irradiation and the effect of deformation. The results indicate that the overaging treatment of 873 K for 1 h produced a precipitate microstructure that improved the plastic instability, overall ductility and fracture toughness.
|Journal||Journal of Nuclear Materials|
|Publication status||Published - 1 Aug 2007|
|Event||12th International Conference on Fusion Reactor Materials (ICFRM-12) - Santa Barbara, United States|
Duration: 4 Dec 2005 → 9 Dec 2005
|Conference||12th International Conference on Fusion Reactor Materials (ICFRM-12)|
|Period||04/12/2005 → 09/12/2005|