b'Figure 2. Stress vs. strain curves for unirradiated (U) and ion-irradiated HT-9 specimens at three different doses: 710-5 dpa (L), 710-4 dpa (M), and 710-3 dpa (H)to significantly differ from bulk, with the magnitude of change Figure 3. Example of a simulationdepending on the alloy and variant.used to calculate hardening due to microstructural features. This specificOverlapping of a portion of the simulation volume involves a singlemicromechanical testing was dislocation (light blue) interacting withpurposefully performed acrossa random distribution of precipitates or voids (red) institutions (University of California, Berkeley and University of Florida) in efforts to probe the fidelity of testing results. This blind testing and data analysis resulted in generally good agreement between instrumentsand analysis techniques at the (304SS, CuCrZr, and HT-9) wheredifferent institutions as well as led samples ranged in thickness fromto identification of areas where 800 m down to 30m using the SS-Jdisagreement can exist and potential sample geometry (Andrew Dong,magnitude of discrepancies.University of California, Berkeley).Beyond mechanical testing, develop-Across the three alloys and sevenment into multiscale modelling and total variants examined, bulk tensileanalysis has also been performed. properties were generally preservedThis includes using discrete disloca-down to thicknesses around 200m. As thickness reduced below 200m,tion dynamics to determine models strength and ductility values beganand fitting parameters for radiation-42 2022|AFC ACCOMPLISHMENTS'