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Behavior of High Burn-up Fuel Cladding under LOCA Conditions

Authors :
Toshinori Chuto
Fumihisa Nagase
Toyoshi Fuketa
Source :
Journal of Nuclear Science and Technology. 46:763-769
Publication Year :
2009
Publisher :
Informa UK Limited, 2009.

Abstract

LOCA-simulated experiments were performed with MDA, ZIRLO™, M5®, NDA, and Zircaloy-2 cladding specimens with local burn-ups ranging from 66 to 76 MWd/kg. Short test rods fabricated with the cladding specimens were heated, isothermally oxidized at 1,459 to 1,480K in steam flow, and finally quenched in flooding water. Rod rupture and subsequent double-sided oxidation of the cladding were also simulated in the experiments. Neither split-fracture nor fragmentation occurred during the quench in the cladding specimens which were oxidized to about 18–27% of the metallic thickness. Accordingly, the fracture boundary, a most important safety issue, is not reduced significantly by the high burn-up and use of the new alloys within the examined scope, although it may be somewhat reduced with pre-hydriding during the reactor operation as observed in unirradiated specimens.

Details

ISSN :
18811248 and 00223131
Volume :
46
Database :
OpenAIRE
Journal :
Journal of Nuclear Science and Technology
Accession number :
edsair.doi...........032a618bec265a6f68e683c8664d814f
Full Text :
https://doi.org/10.1080/18811248.2007.9711583