Abstract
Most fuel channels in Canadian nuclear power reactors are made from Zr-2.5 wt% Nb alloy. The diffusion coefficient for hydrogen in annealed and extruded specimens of this material has been determined over the temperature range 473 to 973 K. It was found to be somewhat greater than the hydrogen diffusion coefficient in zirconium at temperatures less than 723 K but essentially the same at higher temperatures. This result is explained by a simple model based on the microstructure of the material, which consists of elongated α-grains separated by continuous β-filaments. We also determined the diffusion coefficient and terminal solid solubility for hydrogen in Zr-20 wt% Nb, a material having a β-structure; these quantities were required to establish the validity of the model.
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