Castro Bernal, María Vanessa deGarces Usan, José MaríaLeguey Galán, TeresaPareja Pareja, Ramiro2014-12-192014-12-192011-10Journal of Nuclear Materials 442 (2013) Issues 1-3, Supplement 1, November, Pp. 119-1230022-3115https://hdl.handle.net/10016/19806This study is presented of: The Fifteenth International Conference on Fusion Reactor Materials (ICFRM-15) was held October 16–22, 2011, at the Charleston Marriott Hotel in Charleston, South Carolina (American United States).The mechanical characteristics of a model oxide dispersion strengthened (ODS) alloy with nominal composition Fe─12 wt%Cr─0.4 wt%Y₂O₃ were investigated by means of microhardness measurements, tensile tests up to fracture in the temperature range of 298─973 K, and fracture surface analyses. A non-ODS Fe─12 wt%Cr alloy was also studied to assess the real capacity of the oxide dispersion for strengthening the alloy. The materials were produced by mechanical alloying followed by hot isostatic pressing consolidation and heat treatment at 1023 K. The strengthening effect of the oxide nanodispersion was effective at all temperatures studied, although the tensile strength converges towards the one obtained for the reference alloy at higher temperatures. Moreover, the ODS alloys failed prematurely at T < 673 K due to the presence of Y-rich inclusions, as seen in the fracture surface of these alloys.5application/pdfeng© 2013 Elsevier B.Vconference paperFísicaMateriales10.1016/j.jnucmat.2012.12.034open access119123Journal of Nuclear Materials442CC/0000022080