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Hydride-Related Degradation of Spent-Fuel Cladding Under Repository Conditions

Published online by Cambridge University Press:  10 February 2011

H. M. Chung
H. M. Chung*
Affiliation:
Energy Technology Division, Argonne National Laboratory, Argonne, IL 60439heechung@anl.gov
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Abstract

This report summarizes results of an analysis of hydride-related degradation of commercial spent-nuclear-fuel cladding under repository conditions. Based on applicable laboratory data on critical stress intensity obtained under isothermal conditions, occurrence of delayed hydride cracking from the inner-diameter side of cladding is concluded to be extremely unlikely. The key process for potential initiation of delayed hydride cracking at the outer-diameter side is long-term microstructural evolution near the localized regions of concentrated hydrides, i.e., nucleation, growth, and cracking of hydride blisters. Such locally concentrated hydrides are, however, limited to some high-burnup cladding only, and the potential for crack initiation at the outer-diameter side is expected to be insignificant for the majority of spent fuels. Some degree of hydride reorientation could occur in highburnup spent-fuel cladding. However, even if hydride reorientation occurs, accompanying stress-rupture failure in spent fuel cladding is unlikely to occur.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 608: Symposium QQ – Scientific Basis for Nuclear Waste Management XXIII , 1999 , 17
Copyright
Copyright © Materials Research Society 2000

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