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Microstructural comparison of effects of hafnium and titanium additions in spark-plasma-sintered Fe-based oxide-dispersion strengthened alloys

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posted on 13.03.2017 by Yina Huang, Hongtao Zhang, Maria A. Auger, Zuliang Hong, Huanpo Ning, Michael J. Gorley, Patrick S. Grant, Michael J. Reece, Haixue Yan, Steve G. Roberts
Two oxide dispersion strengthened alloys: 14Cr-0.25Y2O3-0.22Hf (wt.%) and Fe-14Cr-0.25Y2O3-0.4Ti (wt.%) were fabricated by mechanical alloying and subsequently consolidated by spark plasma sintering (SPS). Electron backscatter diffraction showed grain sizes in the range 0.5e15 mm in both alloys. Transmission electron microscopy and scanning transmission electron microscopy showed a homogeneous distribution of nano-oxides precipitated during SPS. Using high resolution transmission electron microscopy, energy dispersive X-ray spectroscopy and atom probe tomography, several different oxide phases were found in both alloys, but the majority of dispersoids were Y-Hf-O type in Fe-14Cr-0.25Y2O3-0.22Hf and Y-Ti-O type in Fe-14Cr-0.25Y2O3-0.4Ti. There were a variety of orientation relationships between the different dispersoids and the ferritic matrix. Both alloys had dispersoid densities of ~1023/m3, with average diameters of 4.3 nm and 3.5 nm in the 0.22Hf and 0.4Ti containing alloys, respectively. Per atom added, Hf (0.07 at.%) is suggested to be more potent than Ti (0.46 at.%) in refining the nano-oxides.

Funding

This work was supported by the UK Engineering and Physical Science Research Council (EPSRC) for financial support through grant EP/H018921/1 “Materials Fission and Fusion Power”and RCUK Energy Programme for financial support through grant EP/1501045.

History

School

  • Aeronautical, Automotive, Chemical and Materials Engineering

Department

  • Materials

Published in

Journal of Nuclear Materials

Citation

Huang, Y. ...et al., 2017. Microstructural comparison of effects of hafnium and titanium additions in spark-plasma-sintered Fe-based oxide-dispersion strengthened alloys. Journal of Nuclear Materials, 487, pp. 433–442.

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© The Authors. Published by Elsevier Ltd

Version

NA (Not Applicable or Unknown)

Publisher statement

This work is made available according to the conditions of the Creative Commons Attribution 4.0 International (CC BY 4.0) licence. Full details of this licence are available at: http://creativecommons.org/licenses/ by/4.0/

Acceptance date

20/02/2017

Publication date

2017

Notes

This is an Open Access Article. It is published by Elsevier under the Creative Commons Attribution 4.0 Unported Licence (CC BY). Full details of this licence are available at: http://creativecommons.org/licenses/by/4.0/

ISSN

0022-3115

Language

en

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