Affiliation:
1. North Carolina State University
Abstract
Zirconium (Zr) alloys are best known for their use in nuclear reactor applications. A
hexagonally close-packed structure with a low c/a ratio and very limited slip systems leads to strong
textures in these alloys during fabrication processes. These alloys are used in cladding applications
for encapsulating fuel pellets, and undergo various stress conditions in-service. Hence, it is
necessary to understand the creep properties of Zr alloys to predict the life of reactor claddings. Due
to the unique texture, the creep deformation of these alloys is anisotropic in nature. The texture of
Zircaloys was determined by X-ray diffraction experiments, and expressed in terms of pole figures
and crystalline orientation distribution functions. Biaxial creep testing of thin walled tubing was
used to study the creep anisotropy. Creep loci evaluation based on the experimental data and model
predictions are compared. It is found that the models can predict the creep loci for recrystallized
alloy very well. However, they fail to explain the behavior of the cold worked alloys. When stress
enhancements due to the grain boundary sliding are taken into account, the predicted creep loci
correlated well with that constructed from the experimental data.
Publisher
Trans Tech Publications, Ltd.
Subject
Mechanical Engineering,Mechanics of Materials,Condensed Matter Physics,General Materials Science
Reference13 articles.
1. K.L. Murty: Appl. Mech. Rev. Vol. 46 (1993), p.194.
2. E. Tenckoff: Fifth Conference on Zirconium in the Nuclear Industry, STP 754 (ASTM, 1982) p.5.
3. J.C. Britt and K.L. Murty: Zirconium Alloys for Reactor Components (BARC, Bombay, 1992) p.1.
4. H.J. Bunge: Texture Analysis in Materials Science (Butterworths, London, 1982).
5. B.L. Adams and K.L. Murty: Mater. Sci. Eng. Vol. 70 (1985) p.181.
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