Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation

Kim, Hyosim; Gigax, Jonathan Gregory; El-Atwani, Osman; Chancey, Matthew Ryan; Baldwin, Jon Kevin Scott; Wang, Yongqiang; Maloy, Stuart Andrew

doi:10.1016/j.matchar.2021.110908

Title: Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation

Abstract

In this work, ferritic-martensitic (F/M) HT9 along with fully ferritic HT9 specimens were irradiated using self-ions to 600 peak displacement-per-atom (dpa) at 450 °C. To investigate and minimize the carbon contamination effect on void swelling, two identical F/M HT9 specimens were prepared: one without a coating and the other one with a tungsten and silver coating on the surface prior to irradiation. The specimen without a coating showed carbide formation in the matrix, resulting from carbon contamination during irradiation, with no voids observed. The coated sample did not form matrix carbides, and voids were observed within the irradiated region. The same coating was applied to the ferritic HT9, and void swelling results of both the F/M HT9 and the ferritic HT9 alloys were compared after irradiation. The F/M HT9 exhibited a maximum of 2.6% swelling, while the ferritic HT9 showed a maximum of 0.8% swelling at a 400–500 nm depth, equivalent to 334 local dpa. The results were correlated with the instability of carbides in the ferritic HT9 under irradiation. Carbides in the F/M HT9 and the ferritic HT9 are both M23C6, but the matrix carbides in the ferritic HT9 were less stable under the irradiation, compared to the onesmore »« less

Authors:

^[1];

^[1]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Publication Date:: Sat Jan 16 00:00:00 EST 2021

Research Org.:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States). Center for Integrated Nanotechnologies (CINT)

Sponsoring Org.:: USDOE Laboratory Directed Research and Development (LDRD) Program; USDOE Office of Nuclear Energy (NE); USDOE Office of Science (SC); USDOE National Nuclear Security Administration (NNSA)

OSTI Identifier:: 1762736

Alternate Identifier(s):: OSTI ID: 1778605; OSTI ID: 1778773

Report Number(s):: LA-UR-20-26535
Journal ID: ISSN 1044-5803

Grant/Contract Number:: 89233218CNA000001

Resource Type:: Accepted Manuscript

Journal Name:: Materials Characterization

Additional Journal Information:: Journal Volume: 173; Journal ID: ISSN 1044-5803

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE

Citation Formats


                    Kim, Hyosim, Gigax, Jonathan Gregory, El-Atwani, Osman, Chancey, Matthew Ryan, Baldwin, Jon Kevin Scott, Wang, Yongqiang, and Maloy, Stuart Andrew. Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation.  United States: N. p., 2021. 
Web.  doi:10.1016/j.matchar.2021.110908.

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                    Kim, Hyosim, Gigax, Jonathan Gregory, El-Atwani, Osman, Chancey, Matthew Ryan, Baldwin, Jon Kevin Scott, Wang, Yongqiang, & Maloy, Stuart Andrew. Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation.  United States.  https://doi.org/10.1016/j.matchar.2021.110908

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                    Kim, Hyosim, Gigax, Jonathan Gregory, El-Atwani, Osman, Chancey, Matthew Ryan, Baldwin, Jon Kevin Scott, Wang, Yongqiang, and Maloy, Stuart Andrew. Sat .  
"Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation".  United States.  https://doi.org/10.1016/j.matchar.2021.110908.  https://www.osti.gov/servlets/purl/1762736.

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@article{osti_1762736,

  title        = {Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation},

  author       = {Kim, Hyosim and Gigax, Jonathan Gregory and El-Atwani, Osman and Chancey, Matthew Ryan and Baldwin, Jon Kevin Scott and Wang, Yongqiang and Maloy, Stuart Andrew},

  abstractNote = {In this work, ferritic-martensitic (F/M) HT9 along with fully ferritic HT9 specimens were irradiated using self-ions to 600 peak displacement-per-atom (dpa) at 450 °C. To investigate and minimize the carbon contamination effect on void swelling, two identical F/M HT9 specimens were prepared: one without a coating and the other one with a tungsten and silver coating on the surface prior to irradiation. The specimen without a coating showed carbide formation in the matrix, resulting from carbon contamination during irradiation, with no voids observed. The coated sample did not form matrix carbides, and voids were observed within the irradiated region. The same coating was applied to the ferritic HT9, and void swelling results of both the F/M HT9 and the ferritic HT9 alloys were compared after irradiation. The F/M HT9 exhibited a maximum of 2.6% swelling, while the ferritic HT9 showed a maximum of 0.8% swelling at a 400–500 nm depth, equivalent to 334 local dpa. The results were correlated with the instability of carbides in the ferritic HT9 under irradiation. Carbides in the F/M HT9 and the ferritic HT9 are both M23C6, but the matrix carbides in the ferritic HT9 were less stable under the irradiation, compared to the ones on the grain boundaries in the F/M HT9. The study shows the impact of chemistry on the void swelling which overpowers the microstructural factors such as grain size and phase.},

  doi          = {10.1016/j.matchar.2021.110908},

  journal      = {Materials Characterization},

  number       = ,

  volume       = 173,

  place        = {United States},

  year         = {Sat Jan 16 00:00:00 EST 2021},

  month        = {Sat Jan 16 00:00:00 EST 2021}

}

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Title: Comparison of void swelling of ferritic-martensitic and ferritic HT9 alloys after high-dose self-ion irradiation

Abstract

Citation Formats

Materials challenges in nuclear energy journal, February 2013

Structural materials for fission & fusion energy journal, November 2009

Designing Radiation Resistance in Materials for Fusion Energy journal, July 2014

Ferritic/martensitic steels for next-generation reactors journal, September 2007

Elevated temperature ferritic and martensitic steels and their application to future nuclear reactors journal, October 2005

Microstructural analysis of neutron-irradiated martensitic steels journal, June 1996

Microstructural examination of commercial ferritic alloys at 200 dpa journal, October 1996

Development of martensitic steels for high neutron damage applications journal, December 1996

Development of radiation resistant materials for advanced nuclear power plant journal, May 2006

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Ferritic/martensitic steels – overview of recent results journal, December 2002

Progress and critical issues of reduced activation ferritic/martensitic steel development journal, December 2000

On mechanisms controlling swelling in ferritic and martensitic alloys journal, July 1988

Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C journal, September 2009

Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF journal, July 2011

Phase stability of an HT-9 duct irradiated in FFTF journal, November 2012

Irradiation Effects of ht-9 Martensitic Steel journal, June 2013

The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels journal, February 2017

Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9 journal, July 2015

Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels journal, November 2016

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Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions journal, October 2014

The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 °C journal, October 2015

Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys journal, October 2015

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Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9 journal, April 2019

Resolution of the carbon contamination problem in ion irradiation experiments journal, December 2017

Carbon Contamination During Ion Irradiation - Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels journal, November 2017

Characterization of M2X formed during 5 MeV Fe2+ irradiation journal, March 2017

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Grain boundary structure and properties under external influences journal, September 1986

Achieving Radiation Tolerance through Non-Equilibrium Grain Boundary Structures journal, September 2017

Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission journal, March 2010

Temperature and Dose Dependence of Swelling in 10% and 20% Cold-Worked Type 316 Stainless Steels journal, November 1983

Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions journal, April 2017

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SRIM – The stopping and range of ions in matter (2010) journal, June 2010

On the use of SRIM for computing radiation damage exposure journal, September 2013

Evaluation of effective threshold displacement energies and other data required for the calculation of advanced atomic displacement cross-sections journal, September 2017

Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations journal, January 2018

Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling journal, November 2016

Challenges to the use of ion irradiation for emulating reactor irradiation journal, April 2015

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The resistivity recovery of high purity and carbon doped iron following low temperature electron irradiation journal, January 1983

The Ag−C (Silver-Carbon) system journal, June 1988

Tungsten as material for plasma-facing components in fusion devices journal, August 2011

Solid solution strengthening in Fe-N single crystals journal, July 1968

Ab initio calculations of some atomic and point defect interactions involving C and N in Fe journal, February 2005

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An assessment by activation analysis of the influence of small nitrogen contents on electron-induced void swelling in Fe-Cr-Ni alloys journal, July 1990

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

Materials challenges in nuclear energy
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Microstructural analysis of neutron-irradiated martensitic steels
journal, June 1996

Microstructural examination of commercial ferritic alloys at 200 dpa
journal, October 1996

Development of martensitic steels for high neutron damage applications
journal, December 1996

Development of radiation resistant materials for advanced nuclear power plant
journal, May 2006

Microstructural evolution in irradiated ferritic-martensitic steels: transitions to high dose behaviour
journal, November 1993

Ferritic/martensitic steels – overview of recent results
journal, December 2002

Progress and critical issues of reduced activation ferritic/martensitic steel development
journal, December 2000

On mechanisms controlling swelling in ferritic and martensitic alloys
journal, July 1988

Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155dpa at 443°C
journal, September 2009

Microstructural stability of an HT-9 fuel assembly duct irradiated in FFTF
journal, July 2011

Phase stability of an HT-9 duct irradiated in FFTF
journal, November 2012

Irradiation Effects of ht-9 Martensitic Steel
journal, June 2013

The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels
journal, February 2017

Effect of pre-implanted helium on void swelling evolution in self-ion irradiated HT9
journal, July 2015

Void swelling and microstructure evolution at very high damage level in self-ion irradiated ferritic-martensitic steels
journal, November 2016

Impact of the injected interstitial on the correlation of charged particle and neutron-induced radiation damage
journal, July 1983

Effect of defect imbalance on void swelling distributions produced in pure iron irradiated with 3.5 MeV self-ions
journal, October 2014

The influence of ion beam rastering on the swelling of self-ion irradiated pure iron at 450 °C
journal, October 2015

Effect of irradiation mode on the microstructure of self-ion irradiated ferritic-martensitic alloys
journal, October 2015

Beam-contamination-induced compositional alteration and its neutron-atypical consequences in ion simulation of neutron-induced void swelling
journal, May 2017

Standardization of accelerator irradiation procedures for simulation of neutron induced damage in reactor structural materials
journal, October 2017

Impact of composition modification induced by ion beam Coulomb-drag effects on the nanoindentation hardness of HT9
journal, April 2019

Resolution of the carbon contamination problem in ion irradiation experiments
journal, December 2017

Carbon Contamination During Ion Irradiation - Accurate Detection and Characterization of its Effect on Microstructure of Ferritic/Martensitic Steels
journal, November 2017

Characterization of M2X formed during 5 MeV Fe2+ irradiation
journal, March 2017

Use of double and triple-ion irradiation to study the influence of high levels of helium and hydrogen on void swelling of 8–12% Cr ferritic-martensitic steels
journal, January 2016

Grain boundary structure and properties under external influences
journal, September 1986

Achieving Radiation Tolerance through Non-Equilibrium Grain Boundary Structures
journal, September 2017

Efficient Annealing of Radiation Damage Near Grain Boundaries via Interstitial Emission
journal, March 2010

Temperature and Dose Dependence of Swelling in 10% and 20% Cold-Worked Type 316 Stainless Steels
journal, November 1983

Effect of self-ion irradiation on the microstructural changes of alloy EK-181 in annealed and severely deformed conditions
journal, April 2017

Void swelling of an oxide dispersion strengthened ferritic alloy in a high voltage electron microscope
journal, March 1980

SRIM – The stopping and range of ions in matter (2010)
journal, June 2010

On the use of SRIM for computing radiation damage exposure
journal, September 2013

Evaluation of effective threshold displacement energies and other data required for the calculation of advanced atomic displacement cross-sections
journal, September 2017

Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations
journal, January 2018

Modification of SRIM-calculated dose and injected ion profiles due to sputtering, injected ion buildup and void swelling
journal, November 2016

Challenges to the use of ion irradiation for emulating reactor irradiation
journal, April 2015

Modeling injected interstitial effects on void swelling in self-ion irradiation experiments
journal, April 2016

The resistivity recovery of high purity and carbon doped iron following low temperature electron irradiation
journal, January 1983

The Ag−C (Silver-Carbon) system
journal, June 1988

Tungsten as material for plasma-facing components in fusion devices
journal, August 2011

Solid solution strengthening in Fe-N single crystals
journal, July 1968

Ab initio calculations of some atomic and point defect interactions involving C and N in Fe
journal, February 2005

Effect of W and N on mechanical properties of reduced activation ferritic/martensitic EUROFER-based steel grades
journal, April 2018

An assessment by activation analysis of the influence of small nitrogen contents on electron-induced void swelling in Fe-Cr-Ni alloys
journal, July 1990

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