The ELOCA-A code models the thermomechanical behavior of CANDU fuel elements during high-temperature transients such as loss-of-coolant accidents. Calculations include sheath and pellet temperatures, strains (including creep), sheath oxidation, and beryllium-assisted cracking. The ELOCA-A code was developed by adding axial nodes to the ELOCA·MK2 code, which assumes axially uniform temperatures and strains. Thus, it is now possible to study the effects of axial variations such as end flux peaking, axial variations in the microstructure of Zircaloy due to brazing, axially nonuniform heat transfer, and axially nonuniform cross section due to the presence of appendages. Other features of ELOCA-A include choice of Urbanic-Heidrick or Baker-Just correlations for sheath oxidation and double-sided oxidation of a failed sheath. The ELOCA-A code shows reasonable agreement with axial variations in hoop strains measured at Chalk River Nuclear Laboratories. Calculations for some arbitrary transients confirm that axial variations in initial microstructure and in neutron flux can have a significant effect on fuel temperatures and strains.