Mechanical property testing of irradiated Zircaloy cladding under reactor transient conditions

Robert S. Daum, Saurin Majumda, Hanchung Tsai, Terri S. Bray, Donald A. Koss, Arthur T. Motta, Michael C. Billone

Research output: Contribution to journalConference articlepeer-review

32 Scopus citations


Specimen geometries have been developed to determine the mechanical properties of irradiated Zircaloy cladding subjected to the mechanical conditions and temperatures associated with reactivity-initiated accidents (RIA) and loss-of-coolant accidents (LOCA). Miniature ring-stretch specimens were designed to induce both uniaxial and plane-strain states of stress in the transverse (hoop) direction of the cladding. Also, longitudinal tube specimens were also designed to determine the constitutive properties in the axial direction. Finite-element analysis (FEA) and experimental parameters and results were closely coupled to optimize an accurate determination of the stress-strain response and to induce fracture behavior representative of accident conditions. To determine the constitutive properties, a procedure was utilized to transform measured values of load and displacement to a stress-strain response under complex loading states. Additionally, methods have been developed to measure true plastic strains in the gauge section and the initiation of failure using real-time data analysis software. Strain rates and heating conditions have been selected based on their relevance to the mechanical response and temperatures of the cladding during the accidents.

Original languageEnglish (US)
Pages (from-to)195-210
Number of pages16
JournalASTM Special Technical Publication
Issue number1418
StatePublished - 2002
EventSmall Specimen Test Techniques - Reno, NV, United States
Duration: Jan 23 2000Jan 25 2000

All Science Journal Classification (ASJC) codes

  • General Engineering


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