This study was conducted to eamine the strength properties of pure zirconium and its alloys, Zircaloy-2 and Zircaloy-4, before and after irradiation damage is present in the materials. Examining strength properties after irradiation damage of Zirconium is essential because it is a desired material used for cladding of fuel buddles in nuclear reactors. The strength properties of the materials will be examined using an internal-state variable model and analyzing stress versus strain curves measured before and after irradiation exposure. With the use of a Microsoft Excel-based model and the availble literature data, predictions can be made of the strength properties of the materials at different exposures, temperatures, and strain rates, and some conclusions can be drawn regarding the nature of the irradiation damage.

Analysis of zirconium based alloys using an internal-stat variable model

243rd National Meeting (2012)

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