Abstract
The existing irradiation growth measurements for both annealed and cold-worked Zircaloy are critically reviewed with the aim of presenting the most reliable data for use in reactor design. New results from fuel pins and from two specific experiments are also given. Annealed and CW material differ significantly in their behaviour — the former having a dose exponent of 0.4 and the latter around 0.7 — but there is also considerable scatter amongst the results, which is at present inexplicable. For the purposes of extrapolation, two semi-empirical equations are derived which permit an estimation of the growth strain up to the CSGHWR lifetime to within ±40%.
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