Abstract
The results of microstructural studies of the fragments of E110 alloy fuel rod cladding specimens based on sponge and electrolytic zirconium after the operation as a part of VVER-1000 fuel assemblies with the subsequent creep tests under axial loading are presented. It was shown that, during the creep tests, the studied specimens showed no changes in the chemical composition, average size, and bulk density of the second phases, including radiation-induced ones. It was found that, during the creep tests, dislocation loops were annealed, i.e., an increase occurred in their average size with a simultaneous decrease in bulk density. It was shown that the specimens of fuel rod claddings made of an alloy based on electrolytic zirconium demonstrated more significant creep resistance compared to the sponge-based zirconium alloy specimens, which is related to a higher density of globular β-Nb precipitates in the irradiated electrolytic zirconium specimens.
Published Version
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