b'The HERA project is generating valuable data on reactivity-initiated accident experiments that is enhancing our knowledge of pulse width impacts on fuel performance and safety limits of light water reactor fuel rods.Figure 3. Evolution of fuel radial average enthalpy during the transient for a case targeting 650 J/gUO2 fuel radial average enthalpy increase: (a) for NSRR pulse, (b) for TREAT pulseFigure 4. Cladding failure prediction defined as the maximum failure parameter over the critical value for predicted failure for a case targeting 650 J/gUO 2fuel radial average enthalpy increase: (a) for NSRR pulse, (b) for TREAT pulse2023|AFC ACCOMPLISHMENTS 101'