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Effect of hydrogen on the oxygen embrittlement of beta-quenched Zircaloy-4 fuel cladding

Conference · · Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States)
OSTI ID:6317175

Zircaloy cladding embrittlement was evaluated from data derived from the postirradiation examination of 47 light-water reactor type fuel rods irradiated under postulated accident conditions. The Zircaloy-4 cladding showed rapid oxygenation of the/beta/-phase Zircaloy and hydriding in excess of the pretest characterization. Fuel rods operated with a cladding defect were embrittled to a greater extent than intact rods oxidized under similar conditions. A modified background prior/beta/-phase and precipitation of rim-/alpha/was typically observed in the failure region of breached rods. The fracture resistance of breached rods appears to be related to enhanced hydrogen absorption and its influence on both the/alpha/-phase transformation and /alpha/-morphology during rapid (approximately 100 K/s) quenching. refs 5.

Research Organization:
EG and G, Idaho Falls, Idaho, USA
OSTI ID:
6317175
Report Number(s):
CONF-800834-
Journal Information:
Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States), Journal Name: Am. Soc. Test. Mater., Spec. Tech. Publ.; (United States); ISSN ASTTA
Country of Publication:
United States
Language:
English