Abstract
The mechanical properties, the dislocation structure, and the morphology of phase precipitates in the E110 alloy fuel claddings worked in the fuel assemblies of a VVER-1000 reactor to a fuel burn-out of 20 and 70 (MW day)/kgU are studied. The influence of the thermal conditions that model the fuel element dry storage conditions on the annealing of radiation defects and the recovery of the mechanical properties of the claddings is analyzed.
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