Article ID Journal Published Year Pages File Type
1582991 Materials Science and Engineering: A 2008 8 Pages PDF
Abstract

In the present study the annealing behavior of 60% reduced and stress relieved Zircaloy-4 nuclear fuel cladding tube is studied over a temperature range of 300–1000 °C and an annealing time range of 103 to 105 s. The annealing effects were monitored using Knoop microhardness measurements and flow stress diagrams were developed to study the mechanical anisotropy evolution in the tubing. The determined values of the mechanical anisotropy ratios show that the tubing undergoes a significant mechanical anisotropy evolution during annealing.

Related Topics
Physical Sciences and Engineering Materials Science Materials Science (General)
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