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 language | English |
|---|---|
| Article number | 155469 |
| Journal | Journal of Nuclear Materials |
| Volume | 604 |
| Early online date | Oct 28 2024 |
| DOIs | |
| State | Published - Jan 2025 |
Keywords
- Fuel cladding
- Small scale mechanical testing
- Tensile testing
- Zircaloy
INL Publication Number
- INL/JOU-24-79634
- 182134
Fingerprint
Dive into the research topics of 'Length scale effects of micro- and meso‑scale tensile tests of unirradiated and irradiated Zircaloy-4 cladding'. Together they form a unique fingerprint.Cite this
- APA
- Author
- BIBTEX
- Harvard
- Standard
- RIS
- Vancouver