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-0.3Y2O3 (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.
- Authors:
-
[2];
[2];
- Univ. Carlos III de Madrid (Spain); Univ. of Oxford (United Kingdom)
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- 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:
- 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. https://doi.org/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. https://doi.org/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},
number = C,
volume = 528,
place = {United States},
year = {2019},
month = {10}
}
Free Publicly Available Full Text
Publisher's Version of Record
Other availability
Search WorldCat to find libraries that may hold this journal
Cited by: 13 works
Citation information provided by
Web of Science
Web of Science
Figures / Tables:
Table III: Summary of the cluster composition.
All figures and tables
(11 total)
Save to My Library
You must Sign In or Create an Account in order to save documents to your library.
Works referenced in this record:
Perspective of ODS alloys application in nuclear environments
journal, December 2002
- Ukai, Shigeharu; Fujiwara, Masayuki
- Journal of Nuclear Materials, Vol. 307-311, p. 749-757
Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences
journal, August 2004
- Mansur, L. K.; Rowcliffe, A. F.; Nanstad, R. K.
- Journal of Nuclear Materials, Vol. 329-333
Recent Developments in Irradiation-Resistant Steels
journal, August 2008
- Odette, G. R.; Alinger, M. J.; Wirth, B. D.
- Annual Review of Materials Research, Vol. 38, Issue 1, p. 471-503
Optimization of the chemical composition and manufacturing route for ODS RAF steels for fusion reactor application
journal, April 2009
- Oksiuta, Z.; Baluc, N.
- Nuclear Fusion, Vol. 49, Issue 5
Structural materials for fission & fusion energy
journal, November 2009
- Zinkle, Steven J.; Busby, Jeremy T.
- Materials Today, Vol. 12, Issue 11
Atomic structure of nanoclusters in oxide-dispersion-strengthened steels
journal, October 2011
- Hirata, A.; Fujita, T.; Wen, Y. R.
- Nature Materials, Vol. 10, Issue 12, p. 922-926
Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications
journal, June 2017
- Zinkle, S. J.; Boutard, J. L.; Hoelzer, D. T.
- Nuclear Fusion, Vol. 57, Issue 9
Operating temperature windows for fusion reactor structural materials
journal, November 2000
- Zinkle, S. J.; Ghoniem, N. M.
- Fusion Engineering and Design, Vol. 51-52, p. 55-71
A review of the irradiation evolution of dispersed oxide nanoparticles in the b.c.c. Fe-Cr system: Current understanding and future directions
journal, April 2017
- Wharry, Janelle P.; Swenson, Matthew J.; Yano, Kayla H.
- Journal of Nuclear Materials, Vol. 486
Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT
journal, July 2009
- McClintock, D. A.; Sokolov, M. A.; Hoelzer, D. T.
- Journal of Nuclear Materials, Vol. 392, Issue 2
Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels
journal, March 2013
- Certain, A.; Kuchibhatla, S.; Shutthanandan, V.
- Journal of Nuclear Materials, Vol. 434, Issue 1-3
Characterisation of ODS Fe-14Cr-2W-0.3Ti before and after high temperature triple and low temperature single ion irradiations
journal, February 2018
- Šćepanović, M.; Leguey, T.; Auger, M. A.
- Materials Characterization, Vol. 136
Effect of grain boundary orientation on radiation-induced segregation in a Fe–15.2at.% Cr alloy
journal, May 2013
- Hu, Rong; Smith, George D. W.; Marquis, Emmanuelle A.
- Acta Materialia, Vol. 61, Issue 9
Response of nanostructured ferritic alloys to high-dose heavy ion irradiation
journal, February 2014
- Parish, Chad M.; White, Ryan M.; LeBeau, James M.
- Journal of Nuclear Materials, Vol. 445, Issue 1-3
Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization
journal, November 2018
- Song, Miao; Lear, Calvin R.; Parish, Chad M.
- Journal of Nuclear Materials, Vol. 510
Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors
journal, August 2018
- Prasitthipayong, A.; Frazer, D.; Kareer, A.
- Nuclear Materials and Energy, Vol. 16
SRIM – The stopping and range of ions in matter (2010)
journal, June 2010
- Ziegler, James F.; Ziegler, M. D.; Biersack, J. P.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12
Review of Atom Probe FIB-Based Specimen Preparation Methods
journal, November 2007
- Miller, Michael K.; Russell, Kaye F.; Thompson, Keith
- Microscopy and Microanalysis, Vol. 13, Issue 6
Defining clusters in APT reconstructions of ODS steels
journal, September 2013
- Williams, Ceri A.; Haley, Daniel; Marquis, Emmanuelle A.
- Ultramicroscopy, Vol. 132
Atom Probe Tomography: A Technique for Nanoscale Characterization
journal, June 2004
- Miller, M. K.; Kenik, E. A.
- Microscopy and Microanalysis, Vol. 10, Issue 3
The stability of precipitates in an irradiation environment
journal, September 1972
- Nelson, R. S.; Hudson, J. A.; Mazey, D. J.
- Journal of Nuclear Materials, Vol. 44, Issue 3
Analytical characterization of secondary phases and void distributions in an ultrafine-grained ODS Fe–14Cr model alloy
journal, October 2011
- de Castro, V.; Leguey, T.; Auger, M. A.
- Journal of Nuclear Materials, Vol. 417, Issue 1-3
Effect of the milling atmosphere on the microstructure and mechanical properties of a ODS Fe-14Cr model alloy
journal, August 2016
- Auger, M. A.; de Castro, V.; Leguey, T.
- Materials Science and Engineering: A, Vol. 671
Response of 9Cr-ODS steel to proton irradiation at 400°C
journal, September 2014
- He, Jianchao; Wan, Farong; Sridharan, Kumar
- Journal of Nuclear Materials, Vol. 452, Issue 1-3
Stability of nanoclusters in 14YWT oxide dispersion strengthened steel under heavy ion-irradiation by atom probe tomography
journal, December 2014
- He, Jianchao; Wan, Farong; Sridharan, Kumar
- Journal of Nuclear Materials, Vol. 455, Issue 1-3
The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C
journal, December 2015
- Swenson, M. J.; Wharry, J. P.
- Journal of Nuclear Materials, Vol. 467
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys
journal, April 2011
- Was, Gary S.; Wharry, Janelle P.; Frisbie, Brian
- Journal of Nuclear Materials, Vol. 411, Issue 1-3
Segregation behavior in proton- and heavy-ion-irradiated ferritic–martensitic alloys
journal, June 2011
- Jiao, Z.; Was, G. S.
- Acta Materialia, Vol. 59, Issue 11
Effects of single- and simultaneous triple-ion-beam irradiation on an oxide dispersion-strengthened Fe12Cr steel
journal, December 2014
- de Castro, Vanessa; Lozano-Perez, Sergio; Briceno, Martha
- Journal of Materials Science, Vol. 50, Issue 5
Influences of interstitial and extrusion temperature on grain boundary segregation, Y−Ti−O nanofeatures, and mechanical properties of ferritic steels
journal, July 2018
- Seol, Jae Bok; Haley, Daniel; Hoelzer, David T.
- Acta Materialia, Vol. 153
Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation
journal, March 2008
- Allen, T. R.; Gan, J.; Cole, J. I.
- Journal of Nuclear Materials, Vol. 375, Issue 1
Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation
journal, April 2011
- Choudhury, S.; Barnard, L.; Tucker, J. D.
- Journal of Nuclear Materials, Vol. 411, Issue 1-3
Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature
journal, May 2015
- Allen, Todd R.; Kaoumi, Djamel; Wharry, Janelle P.
- Journal of Materials Research, Vol. 30, Issue 9
Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels
journal, March 2019
- Zheng, Ce; Ke, Jia-Hong; Maloy, Stuart A.
- Scripta Materialia, Vol. 162
Resolution of the carbon contamination problem in ion irradiation experiments
journal, December 2017
- Was, G. S.; Taller, S.; Jiao, Z.
- Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 412
Influence of processing on the microstructure and mechanical properties of 14YWT
journal, April 2016
- Hoelzer, D. T.; Unocic, K. A.; Sokolov, M. A.
- Journal of Nuclear Materials, Vol. 471
Figures/Tables have been extracted from DOE-funded journal article accepted manuscripts.