Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy

Zhang, Dalong; Briggs, Samuel A.; Edmondson, Philip D.; Gussev, Maxim N.; Howard, Richard H.; Field, Kevin G.

doi:10.1016/j.jnucmat.2019.151784

Title: Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy

Abstract

An advanced accident-tolerant FeCrAl alloy, C35 M (Fe–13Cr–10Al–1Mo, at %), and its laser-fusion weldments were studied after neutron irradiation up to 1.8 dpa at 357 °C to evaluate the radiation damage and α'-precipitation kinetics. Results show that the densities of α' in the fusion zone (FZ) and the heat-affected zone (HAZ) were only a third of that in the base material, i.e., 2.3 × 10²⁴m^-3. Here, density of dislocation loops in the FZ and HAZ were less than half of that in base material. The size of α' precipitates and the dislocation loops were found to be smaller in base material, compared to FZ and HAZ. The variances in microstructural response within the different regions were attributed to initial as-welded states of each region, indicating the impact of the pre-irradiation condition on radiation response in FeCrAl alloys.

Authors:

^[1]; Briggs, Samuel A. ^[2];

^[3];

^[3]

Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
Oregon State Univ., Corvallis, OR (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: Tue Sep 03 00:00:00 EDT 2019

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

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1659640

Alternate Identifier(s):: OSTI ID: 1564377

Grant/Contract Number:: AC05-00OR22725; AC05-76RL01830

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 527; Journal Issue: n/a; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; FeCrAl; Accident Tolerant; Welding; Dislocation Loops; Precipitation

Citation Formats


                    Zhang, Dalong, Briggs, Samuel A., Edmondson, Philip D., Gussev, Maxim N., Howard, Richard H., and Field, Kevin G. Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy.  United States: N. p., 2019. 
Web.  doi:10.1016/j.jnucmat.2019.151784.

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                    Zhang, Dalong, Briggs, Samuel A., Edmondson, Philip D., Gussev, Maxim N., Howard, Richard H., & Field, Kevin G. Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy.  United States.  https://doi.org/10.1016/j.jnucmat.2019.151784

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                    Zhang, Dalong, Briggs, Samuel A., Edmondson, Philip D., Gussev, Maxim N., Howard, Richard H., and Field, Kevin G. Tue .  
"Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy".  United States.  https://doi.org/10.1016/j.jnucmat.2019.151784.  https://www.osti.gov/servlets/purl/1659640.

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@article{osti_1659640,

  title        = {Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy},

  author       = {Zhang, Dalong and Briggs, Samuel A. and Edmondson, Philip D. and Gussev, Maxim N. and Howard, Richard H. and Field, Kevin G.},

  abstractNote = {An advanced accident-tolerant FeCrAl alloy, C35 M (Fe–13Cr–10Al–1Mo, at %), and its laser-fusion weldments were studied after neutron irradiation up to 1.8 dpa at 357 °C to evaluate the radiation damage and α'-precipitation kinetics. Results show that the densities of α' in the fusion zone (FZ) and the heat-affected zone (HAZ) were only a third of that in the base material, i.e., 2.3 × 1024m-3. Here, density of dislocation loops in the FZ and HAZ were less than half of that in base material. The size of α' precipitates and the dislocation loops were found to be smaller in base material, compared to FZ and HAZ. The variances in microstructural response within the different regions were attributed to initial as-welded states of each region, indicating the impact of the pre-irradiation condition on radiation response in FeCrAl alloys.},

  doi          = {10.1016/j.jnucmat.2019.151784},

  journal      = {Journal of Nuclear Materials},

  number       = n/a,

  volume       = 527,

  place        = {United States},

  year         = {Tue Sep 03 00:00:00 EDT 2019},

  month        = {Tue Sep 03 00:00:00 EDT 2019}

}

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Title: Influence of welding and neutron irradiation on dislocation loop formation and α' precipitation in a FeCrAl alloy

Abstract

Citation Formats

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

Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA journal, August 1995

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

Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses journal, July 2008

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

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

Heterogeneous dislocation loop formation near grain boundaries in a neutron-irradiated commercial FeCrAl alloy
journal, January 2017

Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations
journal, May 2018

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

Precipitation of α′ in neutron irradiated commercial FeCrAl alloys
journal, January 2018

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

Dislocation loop formation in model FeCrAl alloys after neutron irradiation below 1 dpa
journal, November 2017

Role of refractory inclusions in the radiation-induced microstructure of APMT
journal, July 2018

Dislocation loops and bubbles in oxide dispersion strengthened ferritic steel after helium implantation under stress
journal, January 2008

Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors
journal, January 2015

On the α–α′ miscibility gap of Fe–Cr alloys
journal, December 2008

The 885° f (475° c) embrittlement of ferritic stainless steels
journal, January 1973

The effect of alloying on 485°C embrittlement
journal, August 1976

Impact of neutron irradiation on mechanical performance of FeCrAl alloy laser-beam weldments
journal, June 2018

Al partitioning in MA 956, an ODS ferritic stainless steel
journal, February 1997

Influence of recrystallization on phase separation kinetics of oxide dispersion strengthened Fe–Cr–Al alloy
journal, March 2012

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

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

Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
journal, April 2015

Diffraction contrast STEM of dislocations: Imaging and simulations
journal, August 2011

α′ precipitation in neutron-irradiated Fe–Cr alloys
journal, March 2014

Applications of atom-probe tomography to the characterisation of solute behaviours
journal, July 2010

Microstructural changes in a neutron-irradiated Fe–6 at.%Cr alloy
journal, October 2014

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

Microstructural changes in a neutron-irradiated Fe–15 at.%Cr alloy
journal, November 2014

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

Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA
journal, August 1995

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

Heavy-ion irradiations of Fe and Fe–Cr model alloys Part 1: Damage evolution in thin-foils at lower doses
journal, July 2008

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

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

Ostwald ripening in multicomponent alloys
journal, October 1993

The kinetics of precipitation from supersaturated solid solutions
journal, April 1961

Characterizing nanoscale precipitation in a titanium alloy by laser-assisted atom probe tomography
journal, July 2018

Quantitative binomial distribution analyses of nanoscale like‐solute atom clustering and segregation in atom probe tomography data
journal, July 2008

Analysis of conventional and three‐dimensional atom probe data for multiphase materials
journal, March 1994

Initial clustering – a key factor for phase separation kinetics in Fe–Cr-based alloys
journal, March 2014

Irradiation damage in 304 and 316 stainless steels: experimental investigation and modeling. Part II: Irradiation induced hardening
journal, March 2004

A SANS investigation of the irradiation-enhanced α–α′ phases separation in 7–12 Cr martensitic steels
journal, February 2003

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