Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Investigation of Nano-Scale Segregation in Nanostructured Ferritic Alloy 14YWT after Heavy Ion Irradiation

Journal Article · · Materials
DOI:https://doi.org/10.3390/ma15207257· OSTI ID:2470417
 [1];  [2];  [2];  [1]
  1. Harbin Institute of Technology (China)
  2. Univ. of Science and Technology, Beijing (China)
Oxide-dispersion-strengthened (ODS) steels, which contain nano-scale Y-Ti-O particles, are being considered for high-temperature radiation environments of nuclear reactors. It is important to accurately characterize the structure of grain boundaries and understand the behavior of segregation at grain boundaries in ODS steels during irradiation. The effect of heavy ion irradiation at 700 °C on Nanostructured Ferritic Alloy 14YWT was investigated using Atom Probe Tomography. Enrichment of Cr occurs at the grain boundaries as well as at nano oxide particle surfaces in the unirradiated sample. The enrichment of Ti and Y at a grain boundary corresponds with Y-Ti-O nano oxide particles with larger size compared to those in the grain, and the Cr enrichment is particularly accentuated at these larger nano oxide particles. The segregation of W occurs at the grain boundaries that are without nano oxide particles. O is segregated at grain boundaries without oxide particles after irradiation. The segregation behavior of Cr, W, Ti, and Y at the grain boundary in the irradiated samples is similar to that in the unirradiated sample. The nano oxide particles embedded in the grain boundary are a primary reason for the increase in Cr segregation at the grain boundary.
Research Organization:
Idaho National Laboratory (INL), Idaho Falls, ID (United States); Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Pacific Northwest National Laboratory (PNNL), Richland, WA (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP)
Grant/Contract Number:
AC07-05ID14517
OSTI ID:
2470417
Journal Information:
Materials, Journal Name: Materials Journal Issue: 20 Vol. 15; ISSN 1996-1944
Publisher:
MDPICopyright Statement
Country of Publication:
United States
Language:
English

References (28)

Dispersion behaviour of oxide particles in mechanically alloyed ODS steel journal January 1995
Analysis of Three-dimensional Atom-probe Data by the Proximity Histogram journal September 2000
Atom probe tomography of nanoscale particles in ODS ferritic alloys journal July 2003
Structural materials for fission & fusion energy journal November 2009
Transmission electron microscopy characterization of the nanofeatures in nanostructured ferritic alloy MA957 journal May 2012
Characterization of oxide nanoprecipitates in an oxide dispersion strengthened 14YWT steel using aberration-corrected STEM journal September 2012
Materials challenges in nuclear energy journal February 2013
Response of nanoclusters to heavy-ion irradiation in an Fe-12Cr ODS steel journal November 2021
Microstructural changes of neutron irradiated ODS ferritic and martensitic steels journal August 2004
Characterization of precipitates in MA/ODS ferritic alloys journal June 2006
Influence of particle dispersions on the high-temperature strength of ferritic alloys journal August 2007
Characteristic results and prospects of the 13Cr–1W–0.3Ti–0.3Y2O3 ODS steel journal April 2009
The role of minor alloying elements on the stability and dispersion of yttria nanoclusters in nanostructured ferritic alloys: An ab initio study journal August 2010
High temperature fracture characteristics of a nanostructured ferritic alloy (NFA) journal December 2010
Effects of heavy-ion irradiation on the grain boundary chemistry of an oxide-dispersion strengthened Fe–12wt.% Cr alloy journal October 2011
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys journal April 2011
Effects of heavy-ion irradiation on solute segregation to dislocations in oxide-dispersion-strengthened Eurofer 97 steel journal May 2011
Effect of neutron irradiation on nanoclusters in MA957 ferritic alloys journal November 2011
Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels journal March 2013
Effect of irradiation temperature on microstructure of ferritic-martensitic ODS steel journal September 2017
Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy journal January 2020
Atom probe tomography characterization of high-dose ion irradiated MA957 journal March 2021
On the use of SRIM for computing radiation damage exposure journal September 2013
Atom probe study of radiation induced grain boundary segregation/depletion in a Fe-12%Cr alloy journal May 2012
The effect of Ti on the coarsening behavior of oxygen-rich nanoparticles in oxide-dispersion-strengthened steels after annealing at 1200°C journal July 2012
Core/shell structures of oxygen-rich nanofeatures in oxide-dispersion strengthened Fe–Cr alloys journal November 2008
Recent Developments in Irradiation-Resistant Steels journal August 2008
Analytical characterisation of oxide dispersion strengthened steels for fusion reactors journal April 2011

Similar Records

Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy
Journal Article · Sun Oct 20 20:00:00 EDT 2019 · Journal of Nuclear Materials · OSTI ID:1607192

TEM characterization of 14YWT and 12YWT ODS ferritic alloys neutron irradiated at 500C using in-situ helium injection
Book · Tue Mar 31 00:00:00 EDT 2015 · OSTI ID:1327178