Date of Award


Publication Type

Master Thesis

Degree Name



Mechanical, Automotive, and Materials Engineering


Engineering, Materials Science.



Creative Commons License

Creative Commons Attribution-Noncommercial-No Derivative Works 4.0 License
This work is licensed under a Creative Commons Attribution-Noncommercial-No Derivative Works 4.0 License.


The annealing behaviour of 60% tube reduced and stress relieved Zircaloy-4 nuclear fuel cladding material is studied over the temperature range 300 to 1000$\sp\circ$C for annealing times of 10$\sp3$, 10$\sp4$ and 10$\sp5$ seconds. For annealing temperatures up to 500$\sp\circ$C there is little change in texture and mechanical anisotropy; rather, the tubing becomes softer due to recovery and removal of cold-work. In the temperature range 500 to 800$\sp\circ$C, there is change in microhardness due to recrystallization and grain growth effects. For annealing temperatures above 800$\sp\circ$C, the overall room temperature strength of the tubing is increased due to phase changes and the tubing exhibits a more mechanically anisotropic behaviour. The data on the mechanical anisotropy ratio (minimum/maximum hardness) shows that the recrystallized structure produced at about 500$\sp\circ$C for annealing times 10$\sp3$ and 10$\sp4$ seconds is more mechanically anisotropic than the as-received tubing. (Abstract shortened by UMI.)Dept. of Mechanical, Automotive, and Materials Engineering. Paper copy at Leddy Library: Theses & Major Papers - Basement, West Bldg. / Call Number: Thesis1991 .F375. Source: Masters Abstracts International, Volume: 31-01, page: 0412. Thesis (M.A.Sc.)--University of Windsor (Canada), 1991.