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Length scale effects of micro- and meso‑scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding

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4 Scopus citations

Abstract

Zircaloy-4 is an essential material for cladding structures within fission-based reactors. To explore the changes in properties measured on differing length scales, FIB-machined micro-scale tensile tests were performed on both irradiated and control groups of Zircaloy-4. This was correlated with tensile testing on femtosecond laser-machined meso‑scale specimens. Pronounced size effects were found when varying specimen geometry. Increases in tensile geometry size were associated with a reduction in measured yield stress for both irradiated and unirradiated samples. Meso-scale testing found strength and strain values similar to that of bulk-scale testing.

Original languageEnglish
Article number155469
JournalJournal of Nuclear Materials
Volume604
Early online dateOct 28 2024
DOIs
StatePublished - Jan 2025

Keywords

  • Fuel cladding
  • Small scale mechanical testing
  • Tensile testing
  • Zircaloy

INL Publication Number

  • INL/JOU-24-79634
  • 182134

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