Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa

Field, Kevin G.; Briggs, Samuel A.; Sridharan, Kumar; Yamamoto, Yukinori; Howard, Richard H.

doi:10.1016/j.jnucmat.2017.07.061

Title: Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa

Abstract

FeCrAl alloys with varying compositions and microstructures are under consideration for accident-tolerant fuel cladding, but limited details exist on dislocation loop formation and growth for this class of alloys under neutron irradiation. Four model FeCrAl alloys with chromium contents ranging from 10.01 to 17.51 wt % and alunimum contents of 4.78 to 2.93 wt % were neutron irradiated to doses of 0.3–0.8 displacements per atom (dpa) at temperatures of 335–355°C. On-zone STEM imaging revealed a mixed population of black dots and larger dislocation loops with either a/2< 111 > or a< 100 > Burgers vectors. Weak composition dependencies were observed and varied depending on whether the defect size, number density, or ratio of defect types was of interest. Here, the results were found to mirror those of previous studies on FeCrAl and FeCr alloys irradiated under similar conditions, although distinct differences exist.

Authors:

^[1];

^[2]; Sridharan, Kumar ^[2];

^[1]; Howard, Richard H. ^[1]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Wisconsin-Madison, Madison, WI (United States)

Publication Date:: Tue Aug 01 00:00:00 EDT 2017

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE Office of Science (SC), Basic Energy Sciences (BES)

OSTI Identifier:: 1407805

Alternate Identifier(s):: OSTI ID: 1495576

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 495; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; FeCrAl; Accident tolerant; Dislocation; Radiation effects

Citation Formats


                    Field, Kevin G., Briggs, Samuel A., Sridharan, Kumar, Yamamoto, Yukinori, and Howard, Richard H. Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa.  United States: N. p., 2017. 
Web.  doi:10.1016/j.jnucmat.2017.07.061.

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                    Field, Kevin G., Briggs, Samuel A., Sridharan, Kumar, Yamamoto, Yukinori, & Howard, Richard H. Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa.  United States.  https://doi.org/10.1016/j.jnucmat.2017.07.061

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                    Field, Kevin G., Briggs, Samuel A., Sridharan, Kumar, Yamamoto, Yukinori, and Howard, Richard H. Tue .  
"Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa".  United States.  https://doi.org/10.1016/j.jnucmat.2017.07.061.  https://www.osti.gov/servlets/purl/1407805.

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@article{osti_1407805,

  title        = {Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa},

  author       = {Field, Kevin G. and Briggs, Samuel A. and Sridharan, Kumar and Yamamoto, Yukinori and Howard, Richard H.},

  abstractNote = {FeCrAl alloys with varying compositions and microstructures are under consideration for accident-tolerant fuel cladding, but limited details exist on dislocation loop formation and growth for this class of alloys under neutron irradiation. Four model FeCrAl alloys with chromium contents ranging from 10.01 to 17.51 wt % and alunimum contents of 4.78 to 2.93 wt % were neutron irradiated to doses of 0.3–0.8 displacements per atom (dpa) at temperatures of 335–355°C. On-zone STEM imaging revealed a mixed population of black dots and larger dislocation loops with either a/2< 111 > or a< 100 > Burgers vectors. Weak composition dependencies were observed and varied depending on whether the defect size, number density, or ratio of defect types was of interest. Here, the results were found to mirror those of previous studies on FeCrAl and FeCr alloys irradiated under similar conditions, although distinct differences exist.},

  doi          = {10.1016/j.jnucmat.2017.07.061},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 495,

  place        = {United States},

  year         = {Tue Aug 01 00:00:00 EDT 2017},

  month        = {Tue Aug 01 00:00:00 EDT 2017}

}

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Automated defect analysis in electron microscopic images
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Title: Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa

Abstract

Citation Formats

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding journal, May 2014

Accident tolerant fuels for LWRs: A perspective journal, May 2014

High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments journal, September 2013

Effect of steam on high temperature oxidation behaviour of alumina-forming alloys journal, January 2015

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys journal, October 2015

Irradiation-enhanced α′ precipitation in model FeCrAl alloys journal, April 2016

A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys journal, May 2017

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys journal, June 2017

Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys journal, September 2017

Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors journal, December 2015

Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature journal, March 2016

Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing journal, August 2017

TEM characterization of dislocation loops in irradiated bcc Fe-based steels journal, March 2013

Observation and analysis of defect cluster production and interactions with dislocations journal, August 2004

Electron Radiation Damage of Iron in High Voltage Electron Microscope journal, July 1975

Radiation hardening in neutron-irradiated polycrystalline copper: Barrier strength of defect clusters journal, March 1991

Orientation relationships and interface structure of α′-Cr nanoclusters embedded in α-Fe matrix after α–α′ demixing in neutron irradiated Oxide Dispersion Strengthened material journal, May 2012

Void-swelling in irons and ferritic steels journal, November 1979

Transmission electron microscopy investigation of the microstructure of Fe–Cr alloys induced by neutron and ion irradiation at 300 °C journal, June 2016

Effect of Cr on the mechanical properties and microstructure of Fe–Cr model alloys after n-irradiation journal, June 2008

Post-irradiation deformation in a Fe-9%Cr alloy journal, July 2001

Mechanisms of radiation strengthening in Fe–Cr alloys as revealed by atomistic studies journal, November 2013

Assessment of hardening due to dislocation loops in bcc iron: Overview and analysis of atomistic simulations for edge dislocations journal, May 2016

Application of a three-feature dispersed-barrier hardening model to neutron-irradiated Fe–Cr model alloys journal, May 2014

The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa journal, August 1998

Microstructural examination of neutron-irradiated simple ferritic alloys journal, July 1982

Neutron irradiation effects in Fe and Fe-Cr at 300 °C journal, June 2016

The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures journal, December 2010

Solving the Puzzle of ⟨ 100 ⟩ Interstitial Loop Formation in bcc Iron journal, June 2013

Automated defect analysis in electron microscopic images journal, July 2018

Advanced oxidation-resistant iron-based alloys for LWR fuel cladding
journal, May 2014

Accident tolerant fuels for LWRs: A perspective
journal, May 2014

High temperature oxidation of fuel cladding candidate materials in steam–hydrogen environments
journal, September 2013

Effect of steam on high temperature oxidation behaviour of alumina-forming alloys
journal, January 2015

Radiation tolerance of neutron-irradiated model Fe–Cr–Al alloys
journal, October 2015

Irradiation-enhanced α′ precipitation in model FeCrAl alloys
journal, April 2016

A combined APT and SANS investigation of α′ phase precipitation in neutron-irradiated model FeCrAl alloys
journal, May 2017

Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys
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Dislocation loop evolution during in-situ ion irradiation of model FeCrAl alloys
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Development and property evaluation of nuclear grade wrought FeCrAl fuel cladding for light water reactors
journal, December 2015

Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature
journal, March 2016

Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing
journal, August 2017

TEM characterization of dislocation loops in irradiated bcc Fe-based steels
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Observation and analysis of defect cluster production and interactions with dislocations
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Electron Radiation Damage of Iron in High Voltage Electron Microscope
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Radiation hardening in neutron-irradiated polycrystalline copper: Barrier strength of defect clusters
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Orientation relationships and interface structure of α′-Cr nanoclusters embedded in α-Fe matrix after α–α′ demixing in neutron irradiated Oxide Dispersion Strengthened material
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The microstructure and tensile properties of Fe–Cr alloys after neutron irradiation at 400°C to 5.5–7.1 dpa
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Neutron irradiation effects in Fe and Fe-Cr at 300 °C
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The temperature dependence of heavy-ion damage in iron: A microstructural transition at elevated temperatures
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Solving the Puzzle of $⟨ 100 ⟩$ Interstitial Loop Formation in bcc Iron
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