In the wake of the Fukushima nuclear accident, experimental and modeling efforts were renewed to evaluate the burst behavior of incumbent zirconium and accident-tolerant fuel cladding concepts during loss-of-coolant-accident scenarios.The thermomechanical response of zirconium claddings during accident conditions is multifaceted, and current modeling efforts lack the necessary full-field strain and temperature data to refine predictive capabilities.In this work, coupled digital image correlation and infrared thermography techniques were used to measure cladding strain, temperature, and pressure during burst testing of Zircaloy-4.2D and 3D digital image correlation techniques were applied, and the discrepancies between them were evaluated.