Zirconium Research at Aktiebolaget Atoraenergi, Sweden, Department for Reactor Materials and Fuel Elements

摘要

The general character of the research work in this field is unchanged, the main object being an attempt to provide fundamental information on the pro¬perties of Zircaloy-2 with regard to its use as cladding and as material for construction in water moderated nuclear reactors.nThe previous report contained summaries on Structure, Corrosion, and Mechani¬cal Properties and Deformation. To this is now added Irradiation Behaviour.