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Title: Structure of high-burnup-fuel Zircaloy cladding. [PWR; BWR]

Conference ·
OSTI ID:5914092

Zircaloy cladding from high-burnup (> 20 MWd/kg U) fuel rods in light-water reactors is characterized by a high density of irradiation-induced defects (RID), compositional changes (e.g., oxygen and hydrogen uptake) associated with in-service corrosion, and geometrical changes produced by creepdown, bowing, and irradiation-induced growth. During a reactor power transient, the cladding is subject to localized stress imposed by thermal expansion of the cracked fuel pellets and to mechanical constraints imposed by pellet-cladding friction. As part of a program to provide a better understanding of brittle-type failure of Zircaloy fuel cladding by pellet-cladding interaction (PCI) phenomenon, the stress-rupture properties and microstructural characteristics of high-burnup spent fuel cladding have been under investigation. This paper reports the results of the microstructural examinations by optical microscopy, scanning (SEM), 100-keV transmission (TEM), and 1 MeV high-voltage (HVEM) electron microscopies of the fractured spent fuel cladding with a specific empahsis on a correlation of the structural characteristics with the fracture behavior.

Research Organization:
Argonne National Lab., IL (USA)
DOE Contract Number:
W-31-109-ENG-38
OSTI ID:
5914092
Report Number(s):
CONF-831047-22; ON: DE83014699
Resource Relation:
Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
Country of Publication:
United States
Language:
English