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In-situ Micromechanical Testing of Neutron Irradiated FeCrAl Alloys

Iron-Chromium-Aluminum (FeCrAl) alloys have been selected as one of the candidate accident tolerant fuels (ATFs) claddings to replace Zirconium-based alloys of the current fleet of light water reactors (LWRs). FeCrAl alloys have several advantages such as reasonable irradiation resistance [1,2], superior oxidation and corrosion tolerance [3], as well as good processing and weldability [4]. As a body-centeredcubic (bcc) type alloy, the activation of dislocation slip to which plane is not well defined [5] and the localized strain burst is driven by screw dislocations [6]. After irradiation, a combination of dislocation channeling [7] and strain bursts [8] are affected by irradiation-induced defects. Prior tensile studies of FeCrAl alloys have demonstrated irradiation-induced hardening behavior, but the detailed analysis on the dislocation structure after deformation and the chemical composition have not been fully performed. Due to all these complexities, this study aims to understand the role of irradiation-induced defects on the mechanical response and deformation mechanisms in the FeCrAl alloy system.