Fracture toughness behavior of Zircaloy-4 in the form of fuel cladding tubing in nuclear reactors.
Published: 2004
Language: eng
Number of pages: 121
Description: Based on previous work, a modified VEC technique has been developed in this study. This technique has been proven, through the HCP based Ti3Al2.5V tubing, to be reliable for fracture toughness measurement of thin-walled tubes. The average critical J integral value of unirradiated Zircaloy-4 cladding is hence determined to be 82.6 kN/m, corresponding to a KIC  value of 101.1Mpa.m1/2. The evaluation on microstructure, microhardness, and elastic moduli of the cladding indicates that this material is moderately anisotropic or textured. Fractographic examination of entire fracture surface and crack tip side view demonstrates that the pre-crack fracture is a typical fatigue related fracture since fatigue striations are all over the fracture surface. On the other hand, the J-integral test fracture is of the mixed mode of microvoid coalescence with intergranular fracture since elongated and tear-shaped dimples, secondary cracks, and the zigzag crack propagation path are major features of the corresponding fracture surface.
Notes: Adviser:  Zhirui Wang.

Thesis (M.A.Sc.)--University of Toronto, 2004.

Electronic version licensed for access by U. of T. users.

Source: Masters Abstracts International, Volume: 42-06, page: 2316.

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