skip to main content
OSTI.GOV title logo U.S. Department of Energy
Office of Scientific and Technical Information

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

Journal Article · · Journal of Nuclear Materials

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.

Research Organization:
Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
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
Grant/Contract Number:
AC05-00OR22725; NE0000639; EP/P001645/1; EP/L025817/1; EP/M022803/1
OSTI ID:
1607192
Alternate ID(s):
OSTI ID: 1577898
Journal Information:
Journal of Nuclear Materials, Vol. 528, Issue C; ISSN 0022-3115
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 15 works
Citation information provided by
Web of Science

References (36)

Perspective of ODS alloys application in nuclear environments journal December 2002
Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences journal August 2004
Recent Developments in Irradiation-Resistant Steels journal August 2008
Optimization of the chemical composition and manufacturing route for ODS RAF steels for fusion reactor application journal April 2009
Structural materials for fission & fusion energy journal November 2009
Atomic structure of nanoclusters in oxide-dispersion-strengthened steels journal October 2011
Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications journal June 2017
Operating temperature windows for fusion reactor structural materials journal November 2000
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
Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT journal July 2009
Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels journal March 2013
Characterisation of ODS Fe-14Cr-2W-0.3Ti before and after high temperature triple and low temperature single ion irradiations journal February 2018
Effect of grain boundary orientation on radiation-induced segregation in a Fe–15.2at.% Cr alloy journal May 2013
Response of nanostructured ferritic alloys to high-dose heavy ion irradiation journal February 2014
Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization journal November 2018
Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors journal August 2018
SRIM – The stopping and range of ions in matter (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 https://doi.org/10.1016/j.nimb.2010.02.091
journal June 2010
Review of Atom Probe FIB-Based Specimen Preparation Methods journal November 2007
Defining clusters in APT reconstructions of ODS steels journal September 2013
Atom Probe Tomography: A Technique for Nanoscale Characterization journal June 2004
The stability of precipitates in an irradiation environment journal September 1972
Analytical characterization of secondary phases and void distributions in an ultrafine-grained ODS Fe–14Cr model alloy journal October 2011
Effect of the milling atmosphere on the microstructure and mechanical properties of a ODS Fe-14Cr model alloy journal August 2016
Response of 9Cr-ODS steel to proton irradiation at 400°C journal September 2014
Stability of nanoclusters in 14YWT oxide dispersion strengthened steel under heavy ion-irradiation by atom probe tomography journal December 2014
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
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys journal April 2011
Segregation behavior in proton- and heavy-ion-irradiated ferritic–martensitic alloys journal June 2011
Effects of single- and simultaneous triple-ion-beam irradiation on an oxide dispersion-strengthened Fe12Cr steel journal December 2014
Influences of interstitial and extrusion temperature on grain boundary segregation, Y−Ti−O nanofeatures, and mechanical properties of ferritic steels journal July 2018
Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation journal March 2008
Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation journal April 2011
Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature journal May 2015
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
Resolution of the carbon contamination problem in ion irradiation experiments journal December 2017
Influence of processing on the microstructure and mechanical properties of 14YWT journal April 2016

Figures / Tables (11)


Similar Records

Cold spray manufacturing of oxide-dispersion strengthened (ODS) steels using gas-atomized and ball-milled 14YWT powders
Journal Article · Mon Dec 05 00:00:00 EST 2022 · Journal of Nuclear Materials · OSTI ID:1607192

Report on the Production by Mechanical Alloying of New Heats of 14YWT
Technical Report · Fri Aug 30 00:00:00 EDT 2019 · OSTI ID:1607192

Tensile fracture characteristics of nanostructured ferritic alloy 14YWT
Journal Article · Fri Jan 01 00:00:00 EST 2010 · Journal of Nuclear Materials · OSTI ID:1607192