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Bending Testing and Characterization of Surrogate Nuclear Fuel Rods Made of Zircaloy-4 Cladding and Aluminum Oxide Pellets...

by Hong Wang, Jy-an Wang
Publication Type
Journal
Journal Name
Journal of Nuclear Materials
Publication Date
Page Numbers
470 to 482
Volume
479

Behavior of surrogate nuclear fuel rods made of Zircaloy-4 (Zry-4) cladding with alumina pellets under reversed cyclic bending was studied. Tests were performed under load or moment control at 5 Hz, and an empirical correlation was established between rod fatigue life and amplitude of the applied moment. Fatigue response of Zry-4 cladding was further characterized by using flexural rigidity. Degradation of flexural rigidity was shown to depend on the moment applied and the prefatigue condition of specimens. Pellet-to-pellet interface (PPI), pellet-to-cladding interface (PCI), and pellet condition all affect surrogate rod failure. Bonding/debonding of PPI/PCI and pellet fracturing contribute to surrogate rod bending fatigue. The effect of sensor spacing on curvature measurement using three-point deflections was studied; the method—based on effective specimen gauge length—is effective in sensor spacing correction. The database developed and the understanding gained in this study can serve as input to analysis of SNF vibration integrity.