Grain Refinement and Solute Distribution in Zircaloy-4 Following High-Pressure Torsion

Abstract Zirconium (Zr) alloys, such as Zircaloy-4, are widely used for structural components and fuel cladding in industrial nuclear fission applications. High-pressure torsion (HPT), a severe plastic deformation process, produces an ultra-fine grain structure with properties that may have benefits in the nuclear industry, but the microstructural implications of processing of Zr alloys using this technique have not yet been extensively explored. Here, electron microscopy and atom probe tomography were used to investigate the microstructure and solute distribution in an as-received Zircaloy-4 and a fine-grained HPT-processed sample. Fe segregates to grain boundaries in both samples, however, at much lower concentrations after HPT processing, indicating that Fe diffuses to the newly formed grain boundaries during the severe plastic deformation. Although Sn segregates to the grain boundaries of the as-received sample, it is distributed almost homogenously in the HPT-processed sample, which may provide advantages for corrosion resistance. Very low concentrations of Cr alloying elements at the matrix and grain boundaries of both samples are attributed to precipitation.

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Publication Details

Journal
Journal of Materials Engineering and Performance
Published
2025-04-25
DOI
https://doi.org/10.1007/s11665-025-11225-2
Citations
1
Primary Topic
Nuclear Materials and Properties
Type
article
Field-Weighted Citation Impact
0.52

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article

Grain Refinement and Solute Distribution in Zircaloy-4 Following High-Pressure Torsion

Patrick A. Burr, Levi Tegg, Limei Yang, Ingrid McCarroll et al.
1 citations
Journal of Materials Engineering and Performance
Nuclear Materials and Properties
0.52
article

Grain Refinement and Solute Distribution in Zircaloy-4 Following High-Pressure Torsion

Patrick A. Burr, Levi Tegg, Limei Yang, Ingrid McCarroll, Sima Aminorroaya Yamini, Yi Huang, Siyu Huang, Julie M. Cairney, Ondrej Muránsky, Zhiyang Wang
article en
1 citations

Abstract

Abstract Zirconium (Zr) alloys, such as Zircaloy-4, are widely used for structural components and fuel cladding in industrial nuclear fission applications. High-pressure torsion (HPT), a severe plastic deformation process, produces an ultra-fine grain structure with properties that may have benefits in the nuclear industry, but the microstructural implications of processing of Zr alloys using this technique have not yet been extensively explored. Here, electron microscopy and atom probe tomography were used to investigate the microstructure and solute distribution in an as-received Zircaloy-4 and a fine-grained HPT-processed sample. Fe segregates to grain boundaries in both samples, however, at much lower concentrations after HPT processing, indicating that Fe diffuses to the newly formed grain boundaries during the severe plastic deformation. Although Sn segregates to the grain boundaries of the as-received sample, it is distributed almost homogenously in the HPT-processed sample, which may provide advantages for corrosion resistance. Very low concentrations of Cr alloying elements at the matrix and grain boundaries of both samples are attributed to precipitation.

Journal of Materials Engineering and PerformanceVol. 34(13)
University of Technology Sydney (AU), The University of Sydney (AU), Australian Nuclear Science and Technology Organisation (AU), UNSW Sydney (AU), Max-Planck-Institut für Nachhaltige Materialien (DE), University of Southampton (GB), Bournemouth University (GB)
University of Sydney
Openalex Percentile: Top 39%
Nuclear Materials and Properties
0.52
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