Abstract

The ingress of hydrogen during corrosion in service can degrade the mechanical properties of zirconium alloy nuclear fuel cladding because of the formation of brittle hydrides. The formation of these hydrides is reviewed in light of recent synchrotron radiation experimental results and phase-field modeling computational results that provide new insight on the process.

Original languageEnglish (US)
Pages (from-to)1403-1408
Number of pages6
JournalJOM
Volume64
Issue number12
DOIs
StatePublished - Dec 2012

All Science Journal Classification (ASJC) codes

  • General Materials Science
  • General Engineering

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