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

Title: Irradiation-enhanced α' precipitation in model FeCrAl alloys

Journal Article · · Scripta Materialia
 [1];  [2];  [1];  [1];  [3];  [1];  [1]
  1. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
  2. Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Wisconsin, Madison, WI (United States)
  3. Univ. of Wisconsin, Madison, WI (United States)

We have irradiated the model FeCrAl alloys with varying compositions (Fe(10–18)Cr(10–6)Al at.%) with a neutron at ~ 320 to damage levels of ~ 7 displacements per atom (dpa) to investigate the compositional influence on the formation of irradiation-induced Cr-rich α' precipitates using atom probe tomography. In all alloys, significant number densities of these precipitates were observed. Cluster compositions were investigated and it was found that the average cluster Cr content ranged between 51.1 and 62.5 at.% dependent on initial compositions. Furthermore, this is significantly lower than the Cr-content of α' in binary FeCr alloys. As a result, significant partitioning of the Al from the α' precipitates was also observed.

Research Organization:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Organization:
USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC), Basic Energy Sciences (BES)
Grant/Contract Number:
AC05-00OR22725; AC07-051D14517
OSTI ID:
1238750
Alternate ID(s):
OSTI ID: 1337414
Journal Information:
Scripta Materialia, Vol. 116, Issue C; ISSN 1359-6462
Publisher:
ElsevierCopyright Statement
Country of Publication:
United States
Language:
English
Citation Metrics:
Cited by: 106 works
Citation information provided by
Web of Science

References (18)

Materials challenges in nuclear energy journal February 2013
Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys journal October 2015
High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments journal September 2013
Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors journal December 2015
Microstructural stability of Fe–Cr–Al alloys at 450–550 °C journal February 2015
Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors journal January 2015
Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress journal January 2008
Void-swelling in irons and ferritic steels journal November 1979
Microstructural changes in a neutron-irradiated Fe–15 at.%Cr alloy journal November 2014
α′ precipitation in neutron-irradiated Fe–Cr alloys journal March 2014
Phase separation kinetics in a Fe–Cr–Al alloy journal July 2012
Influence of recrystallization on phase separation kinetics of oxide dispersion strengthened Fe–Cr–Al alloy journal March 2012
Mapping of 475°C embrittlement in ferritic Fe–Cr–Al alloys journal November 2010
Precipitation in iron–chromium–aluminium alloys journal June 1984
LAMDA: Irradiated-Materials Microscopy at Oak Ridge National Laboratory journal August 2015
Atom probe specimen preparation with a dual beam SEM/FIB miller journal September 2007
A sensitivity analysis of the maximum separation method for the characterisation of solute clusters journal May 2011
A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels journal February 2003

Cited By (3)

Vacancy and interstitial atom evolution with the separation of the nanoscale phase in Fe–Cr alloys: phase-field simulations journal January 2020
α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys journal June 2019
Influence of Al Addition Strategy on the Microstructure of a Low‐Cr Oxide Dispersion‐Strengthened Ferritic Steel journal December 2019