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Title: Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy

Abstract

In this work, the nanoscale microstructure of an advanced oxide dispersion strengthened (ODS) 14YWT ferritic alloy (SM13 heat) with nominal composition Fe–14Cr–3W-0.4Ti-0.3Y 2O 3 (wt. %) has been characterized by atom probe tomography (APT) before and after ion irradiation with 70 MeV Fe 9+ ions at 450 °C to a total dose of 21 dpa. A detailed solute cluster analysis of APT data reveals that, in the manufacturing process, larger nanoparticles form in or close to the grain boundaries respective to those inside grains. The evolution of the nanoparticles after irradiation seems to be related to their location, as a higher increase in the number density and in the Y:Ti ratio is observed for the nanoparticles in or close to grain boundaries. Furthermore, APT analysis also shows Cr, W and C segregation to grain boundaries enhanced by the irradiation. A previous study of this same alloy before and after irradiation reports that the mechanical properties do not seem to be affected, but the microstructure was not investigated to confirm. The present work confirms little microstructural evolution after irradiation in this 14YWT alloy, indicating tolerance at the given irradiation conditions.

Authors:
 [1]; ORCiD logo [2]; ORCiD logo [2];  [3]
  1. Univ. Carlos III de Madrid (Spain); Univ. of Oxford (United Kingdom)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  3. Univ. of Oxford (United Kingdom)
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
Engineering and Physical Sciences Research Council (EPSRC); USDOE Office of Nuclear Energy (NE). Nuclear Energy University Program (NEUP); Comunidad Autonoma de Madrid-Spain; Henry Royce Institute for Advanced Materials
OSTI Identifier:
1607192
Alternate Identifier(s):
OSTI ID: 1577898
Grant/Contract Number:  
AC05-00OR22725; NE0000639; EP/P001645/1; EP/L025817/1; EP/M022803/1
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Volume: 528; Journal Issue: C; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 14YWT; ODS alloys; Atom probe tomography; Ion irradiation; Clusters

Citation Formats

Auger, Maria A., Hoelzer, David T., Field, Kevin G., and Moody, Michael P. Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy. United States: N. p., 2019. Web. doi:10.1016/j.jnucmat.2019.151852.
Auger, Maria A., Hoelzer, David T., Field, Kevin G., & Moody, Michael P. Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy. United States. doi:10.1016/j.jnucmat.2019.151852.
Auger, Maria A., Hoelzer, David T., Field, Kevin G., and Moody, Michael P. Mon . "Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy". United States. doi:10.1016/j.jnucmat.2019.151852. https://www.osti.gov/servlets/purl/1607192.
@article{osti_1607192,
title = {Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy},
author = {Auger, Maria A. and Hoelzer, David T. and Field, Kevin G. and Moody, Michael P.},
abstractNote = {In this work, the nanoscale microstructure of an advanced oxide dispersion strengthened (ODS) 14YWT ferritic alloy (SM13 heat) with nominal composition Fe–14Cr–3W-0.4Ti-0.3Y2O3 (wt. %) has been characterized by atom probe tomography (APT) before and after ion irradiation with 70 MeV Fe9+ ions at 450 °C to a total dose of 21 dpa. A detailed solute cluster analysis of APT data reveals that, in the manufacturing process, larger nanoparticles form in or close to the grain boundaries respective to those inside grains. The evolution of the nanoparticles after irradiation seems to be related to their location, as a higher increase in the number density and in the Y:Ti ratio is observed for the nanoparticles in or close to grain boundaries. Furthermore, APT analysis also shows Cr, W and C segregation to grain boundaries enhanced by the irradiation. A previous study of this same alloy before and after irradiation reports that the mechanical properties do not seem to be affected, but the microstructure was not investigated to confirm. The present work confirms little microstructural evolution after irradiation in this 14YWT alloy, indicating tolerance at the given irradiation conditions.},
doi = {10.1016/j.jnucmat.2019.151852},
journal = {Journal of Nuclear Materials},
issn = {0022-3115},
number = C,
volume = 528,
place = {United States},
year = {2019},
month = {10}
}

Journal Article:
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