Hydride-related degradation of spent-fuel cladding under repository conditions
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 and propagation at the outer-diameter side is expected to be insignificant for most spent fuels. Some degree of hydride reorientation could occur in high-burnup spent-fuel cladding. However, even if hydride reorientation occurs, accompanying stress-rupture failure in spent-fuel cladding is unlikely to occur.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 754469
- Report Number(s):
- ANL/ET/CP-100040; TRN: US0002680
- Resource Relation:
- Conference: MRS '99 Fall Meeting, Boston, MA (US), 11/29/1999--12/03/1999; Other Information: PBD: 3 Apr 2000
- Country of Publication:
- United States
- Language:
- English
Similar Records
A Probabilistic-Micro-mechanical Methodology for Assessing Zirconium Alloy Cladding Failure
Potential corrosion and degradation mechanisms of Zircaloy cladding on spent nuclear fuel in a tuff repository