Iron-chromium-aluminum (FeCrAl) alloys arepromising as an accident-tolerant fuel cladding for lossof-coolant accident scenarios; however, limited data areavailable on the acting deformation mechanisms for thisclass of materials after neutron irradiation. Here, in situtensile test experiments were conducted with specimensirradiated at ~1.8 dpa at typical light water reactortemperatures. Selected regions of interest were examinedat different strain levels, aiming to investigate the impactof irradiation on acting deformation mechanisms. Thefine material microstructure was investigated viatransmission electron microscopy. Dislocation structure,radiation-induced defects, and α′-phase morphology wereinvestigated in detail and compared with scanningelectron microscopy-electron backscatter diffraction andmechanical test results.
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