Microchemical evolution of irradiated additive-manufactured HT9

Xiu, Pengyuan; Massey, Caleb; Green, Theresa Mary Kelsy; Taller, Stephen; Isheim, Dieter; Sridharan, Niyanth; Field, Kevin G.

doi:10.1016/j.jnucmat.2021.153410

Title: Microchemical evolution of irradiated additive-manufactured HT9

Abstract

The microstructural responses under 5 MeV Fe2⁺ single-ion-beam irradiation of three conditions of additive-manufactured (AM) HT9 steel using a powder-based directed energy deposition (DED) technique with and without postbuild heat treatments were investigated. Besides the observed dislocation loop formation and the absence of cavities at the irradiation condition of 50 dpa at 460 °C, Ni/Si/Mn-rich precipitates are found to form in all three conditions of AM-HT9, whereas Cu-rich clusters that arise from Cu uptake from the DED process are only observed in the heat-treated conditions, and not in the as-built (ASB) condition. Coprecipitation of the Cu- and Ni/Si/Mn-rich clusters occur near defect sinks such as line dislocations and grain boundaries in the heat-treated AM-HT9. The variation in microchemical evolution can be directly linked to the starting sink strength of the three AM-HT9 conditions, and the ASB condition with higher sink strength suppressed the responses observed in the postbuild heat-treated specimens.

Authors:

Xiu, Pengyuan ^[1]; Massey, Caleb ^[2]; Green, Theresa Mary Kelsy ^[1];

^[3]; Isheim, Dieter ^[4]; Sridharan, Niyanth ^[5]; Field, Kevin G. ^[6]

Univ. of Michigan, Ann Arbor, MI (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Michigan, Ann Arbor, MI (United States)
Northwestern Univ., Evanston, IL (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Lincoln Electric Company (India) Private Limited, Tamil Nadu (India)
Univ. of Michigan, Ann Arbor, MI (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Publication Date:: Sat Nov 20 00:00:00 EST 2021

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

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

OSTI Identifier:: 1847540

Grant/Contract Number:: AC05-00OR22725; AC07-051D14517

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 559; Journal Issue: 1; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; 42 ENGINEERING; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Additive Manufacturing; Ferritic-Martensitic HT9 Steel; Irradiation; Clustering; Precipitation

Citation Formats


                    Xiu, Pengyuan, Massey, Caleb, Green, Theresa Mary Kelsy, Taller, Stephen, Isheim, Dieter, Sridharan, Niyanth, and Field, Kevin G. Microchemical evolution of irradiated additive-manufactured HT9.  United States: N. p., 2021. 
Web.  doi:10.1016/j.jnucmat.2021.153410.

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                    Xiu, Pengyuan, Massey, Caleb, Green, Theresa Mary Kelsy, Taller, Stephen, Isheim, Dieter, Sridharan, Niyanth, & Field, Kevin G. Microchemical evolution of irradiated additive-manufactured HT9.  United States.  https://doi.org/10.1016/j.jnucmat.2021.153410

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                    Xiu, Pengyuan, Massey, Caleb, Green, Theresa Mary Kelsy, Taller, Stephen, Isheim, Dieter, Sridharan, Niyanth, and Field, Kevin G. Sat .  
"Microchemical evolution of irradiated additive-manufactured HT9".  United States.  https://doi.org/10.1016/j.jnucmat.2021.153410.  https://www.osti.gov/servlets/purl/1847540.

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@article{osti_1847540,

  title        = {Microchemical evolution of irradiated additive-manufactured HT9},

  author       = {Xiu, Pengyuan and Massey, Caleb and Green, Theresa Mary Kelsy and Taller, Stephen and Isheim, Dieter and Sridharan, Niyanth and Field, Kevin G.},

  abstractNote = {The microstructural responses under 5 MeV Fe2+ single-ion-beam irradiation of three conditions of additive-manufactured (AM) HT9 steel using a powder-based directed energy deposition (DED) technique with and without postbuild heat treatments were investigated. Besides the observed dislocation loop formation and the absence of cavities at the irradiation condition of 50 dpa at 460 °C, Ni/Si/Mn-rich precipitates are found to form in all three conditions of AM-HT9, whereas Cu-rich clusters that arise from Cu uptake from the DED process are only observed in the heat-treated conditions, and not in the as-built (ASB) condition. Coprecipitation of the Cu- and Ni/Si/Mn-rich clusters occur near defect sinks such as line dislocations and grain boundaries in the heat-treated AM-HT9. The variation in microchemical evolution can be directly linked to the starting sink strength of the three AM-HT9 conditions, and the ASB condition with higher sink strength suppressed the responses observed in the postbuild heat-treated specimens.},

  doi          = {10.1016/j.jnucmat.2021.153410},

  journal      = {Journal of Nuclear Materials},

  number       = 1,

  volume       = 559,

  place        = {United States},

  year         = {Sat Nov 20 00:00:00 EST 2021},

  month        = {Sat Nov 20 00:00:00 EST 2021}

}

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Acta Materialia, Vol. 59, Issue 11
DOI: 10.1016/j.actamat.2011.03.070

Modeling the impact of radiation-enhanced diffusion on implanted ion profiles
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Doyle, Peter J.; Benensky, Kelsa M.; Zinkle, Steven J.
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Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
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Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations
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Emulation of fast reactor irradiated T91 using dual ion beam irradiation
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The rate theory of swelling due to void growth in irradiated metals
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Brailsford, A. D.; Bullough, R.
Journal of Nuclear Materials, Vol. 44, Issue 2
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Behaviour of different ferritic steels under ion, electron and fast neutron irradiation
journal, July 1988

Gilbon, D.; Rivera, C.
Journal of Nuclear Materials, Vol. 155-157
DOI: 10.1016/0022-3115(88)90509-0

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Title: Microchemical evolution of irradiated additive-manufactured HT9

Abstract

Citation Formats

Microstructural development in reduced activation ferritic alloys irradiated to 200 dpa at 420°C journal, September 1994

Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations journal, August 2018

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

Characterization of radiation induced defects in EUROFER 97 after neutron irradiation journal, October 2011

Vacancy–solute interactions in ferromagnetic and paramagnetic bcc iron: Ab initio calculations journal, December 2011

Synthesis of atom probe experiments on irradiation-induced solute segregation in French ferritic pressure vessel steels journal, August 2000

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

Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ~ 400°C journal, September 1994

Influence of the copper impurity level on the irradiation response of reactor pressure vessel steels investigated by SANS journal, June 2012

Irradiation creep and void swelling of two LMR heats of HT9 at ∼ 400°C and 165 dpa journal, October 1996

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

Synergistic effect of displacement damage and helium atoms on radiation hardening in F82H at TIARA facility journal, August 2004

Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys journal, April 2021

Impact properties of irradiated HT9 from the fuel duct of FFTF journal, February 2012

Copper precipitate hardening of irradiated RPV materials and implications on the superposition law and re-irradiation kinetics journal, October 2005

Atom probe characterisation of segregation driven Cu and Mn–Ni–Si co-precipitation in neutron irradiated T91 tempered-martensitic steel journal, December 2020

Thermodynamic and kinetic modeling of Mn-Ni-Si precipitates in low-Cu reactor pressure vessel steels journal, October 2017

Crystallographic texture control in electron beam additive manufacturing via conductive manipulation journal, October 2020

Mechanical properties and microstructure in low-activation martensitic steels F82H and Optimax after 800-MeV proton irradiation journal, December 2000

Corrosion of ferritic–martensitic steel HT9 in supercritical water journal, November 2006

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

On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models journal, December 2019

Spatial variation in void volume during charged particle bombardment — the effects of injected interstitials journal, December 1979

Impurity effects on reduced-activation ferritic steels developed for fusion applications journal, August 2000

Advances in additive manufacturing of metal-based functionally graded materials journal, January 2020

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

A Road Map for the Advanced Manufacturing of Ferritic-Martensitic Steels journal, May 2019

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

Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water journal, September 2007

Microstructural evolution of neutron-irradiated T91 and NF616 to ∼4.3 dpa at 469 °C journal, September 2017

Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing journal, August 2019

Heterogeneous irradiation-induced copper precipitation in ferritic iron–copper model alloys journal, June 2006

Radiation hardening and -embrittlement due to He production in F82H steel irradiated at 250°C in JMTR journal, August 2005

Modeling dislocation evolution in irradiated alloys journal, July 1990

On α′ precipitate composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys journal, March 2018

An Atom Probe Tomography Study of the Through Wall Attenuation Effect on Cu-rich Precipitate Formation in a Reactor Pressure Vessel Steel journal, March 2021

Evolution of weld metals nanostructure and properties under irradiation and recovery annealing of VVER-type reactors journal, March 2013

Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors journal, December 2012

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

Radiation-induced segregation in HT-9 martensitic steel journal, November 1986

A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels journal, February 2013

On the effect of dose rate on irradiation hardening of RPV steels journal, February 2005

Temperature dependence of irradiation hardening due to dislocation loops and precipitates in RPV steels and model alloys journal, September 2015

Nanoscale characterisation of ODS–Eurofer 97 steel: An atom-probe tomography study journal, May 2010

Radiation resistance of weld joints of type 316 stainless steel containing about 10 appm He journal, December 2000

Phase stability in proton and heavy ion irradiated ferritic–martensitic alloys journal, December 2011

Effect of laser welding parameters on fusion zone shape and solidification structure of austenitic stainless steels journal, August 1997

Influence of interface sink strength on the reduction of radiation-induced defect concentrations and fluxes in materials with large interface area per unit volume journal, September 2011

The application of martensitic stainless steels in long lifetime fusion first wall/blankets journal, December 1979

Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments journal, October 2020

He ion irradiation response of a gradient T91 steel journal, September 2020

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

The Role of Co-injected Helium on Swelling and Cavity Evolution at High Damage Levels in Ferritic-Martensitic Steels journal, July 2021

Low-temperature solubility of copper in iron: experimental study using thermoelectric power, small angle X-ray scattering and tomographic atom probe journal, July 2005

Irradiation-induced Cu aggregations in Fe: An origin of embrittlement of reactor pressure vessel steels journal, March 2001

Analysis of Three-dimensional Atom-probe Data by the Proximity Histogram journal, September 2000

Radiation instability of equal channel angular extruded T91 at ultra-high damage levels journal, June 2017

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

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

LAMDA: Irradiated-Materials Microscopy at Oak Ridge National Laboratory journal, August 2015

Microstructural development in advanced ferritic–martensitic steel HCM12A journal, June 2006

HT9 swelling in high burnup fast reactor fuel pin components journal, June 2019

Additive manufacturing of steels: a review of achievements and challenges journal, August 2020

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature journal, January 2020

Cladding and duct materials for advanced nuclear recycle reactors journal, January 2008

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose journal, September 2019

Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System journal, December 2021

Direct Observation of Sink-Dependent Defect Evolution in Nanocrystalline Iron under Irradiation journal, May 2017

CuMnNiSi precipitate evolution in irradiated reactor pressure vessel steels: Integrated Cluster Dynamics and experiments journal, November 2019

Microstructure, Residual Strain and Stress Corrosion Cracking Behavior in 316L Heat-Affected Zone journal, July 2016

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

Precipitate evolution in ion-irradiated HCM12A journal, June 2012

Embrittlement of RPV steels: An atom probe tomography perspective journal, September 2007

Vanadium diffusion coating on HT-9 cladding for mitigating the fuel cladding chemical interactions journal, August 2014

Effects of 3d electron configurations on helium bubble formation and void swelling in concentrated solid-solution alloys journal, December 2019

Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel journal, August 2017

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

Microstructural development in reduced activation ferritic alloys irradiated to 200 dpa at 420°C
journal, September 1994

Enhanced void swelling in NiCoFeCrPd high-entropy alloy by indentation-induced dislocations
journal, August 2018

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

Characterization of radiation induced defects in EUROFER 97 after neutron irradiation
journal, October 2011

Vacancy–solute interactions in ferromagnetic and paramagnetic bcc iron: Ab initio calculations
journal, December 2011

Synthesis of atom probe experiments on irradiation-induced solute segregation in French ferritic pressure vessel steels
journal, August 2000

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

Irradiation creep and swelling of the US fusion heats of HT9 and 9Cr-1Mo to 208 dpa at ~ 400°C
journal, September 1994

Influence of the copper impurity level on the irradiation response of reactor pressure vessel steels investigated by SANS
journal, June 2012

Irradiation creep and void swelling of two LMR heats of HT9 at ∼ 400°C and 165 dpa
journal, October 1996

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

Synergistic effect of displacement damage and helium atoms on radiation hardening in F82H at TIARA facility
journal, August 2004

Temperature-dependent cavity swelling in dual-ion irradiated Fe and Fe-Cr ferritic alloys
journal, April 2021

Impact properties of irradiated HT9 from the fuel duct of FFTF
journal, February 2012

Copper precipitate hardening of irradiated RPV materials and implications on the superposition law and re-irradiation kinetics
journal, October 2005

Atom probe characterisation of segregation driven Cu and Mn–Ni–Si co-precipitation in neutron irradiated T91 tempered-martensitic steel
journal, December 2020

Thermodynamic and kinetic modeling of Mn-Ni-Si precipitates in low-Cu reactor pressure vessel steels
journal, October 2017

Crystallographic texture control in electron beam additive manufacturing via conductive manipulation
journal, October 2020

Mechanical properties and microstructure in low-activation martensitic steels F82H and Optimax after 800-MeV proton irradiation
journal, December 2000

Corrosion of ferritic–martensitic steel HT9 in supercritical water
journal, November 2006

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

On the history and status of reactor pressure vessel steel ductile to brittle transition temperature shift prediction models
journal, December 2019

Spatial variation in void volume during charged particle bombardment — the effects of injected interstitials
journal, December 1979

Impurity effects on reduced-activation ferritic steels developed for fusion applications
journal, August 2000

Advances in additive manufacturing of metal-based functionally graded materials
journal, January 2020

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

A Road Map for the Advanced Manufacturing of Ferritic-Martensitic Steels
journal, May 2019

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

Oxidation of ferritic–martensitic alloys T91, HCM12A and HT-9 in supercritical water
journal, September 2007

Microstructural evolution of neutron-irradiated T91 and NF616 to ∼4.3 dpa at 469 °C
journal, September 2017

Performance of a ferritic/martensitic steel for nuclear reactor applications fabricated using additive manufacturing
journal, August 2019

Heterogeneous irradiation-induced copper precipitation in ferritic iron–copper model alloys
journal, June 2006

Radiation hardening and -embrittlement due to He production in F82H steel irradiated at 250°C in JMTR
journal, August 2005

Modeling dislocation evolution in irradiated alloys
journal, July 1990

On α′ precipitate composition in thermally annealed and neutron-irradiated Fe- 9-18Cr alloys
journal, March 2018

An Atom Probe Tomography Study of the Through Wall Attenuation Effect on Cu-rich Precipitate Formation in a Reactor Pressure Vessel Steel
journal, March 2021

Evolution of weld metals nanostructure and properties under irradiation and recovery annealing of VVER-type reactors
journal, March 2013

Mechanical Performance of Ferritic Martensitic Steels for High Dose Applications in Advanced Nuclear Reactors
journal, December 2012

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

Radiation-induced segregation in HT-9 martensitic steel
journal, November 1986

A physically-based correlation of irradiation-induced transition temperature shifts for RPV steels
journal, February 2013

On the effect of dose rate on irradiation hardening of RPV steels
journal, February 2005

Temperature dependence of irradiation hardening due to dislocation loops and precipitates in RPV steels and model alloys
journal, September 2015

Nanoscale characterisation of ODS–Eurofer 97 steel: An atom-probe tomography study
journal, May 2010

Radiation resistance of weld joints of type 316 stainless steel containing about 10 appm He
journal, December 2000

Phase stability in proton and heavy ion irradiated ferritic–martensitic alloys
journal, December 2011

Effect of laser welding parameters on fusion zone shape and solidification structure of austenitic stainless steels
journal, August 1997

Influence of interface sink strength on the reduction of radiation-induced defect concentrations and fluxes in materials with large interface area per unit volume
journal, September 2011

The application of martensitic stainless steels in long lifetime fusion first wall/blankets
journal, December 1979

Understanding bubble and void nucleation in dual ion irradiated T91 steel using single parameter experiments
journal, October 2020

He ion irradiation response of a gradient T91 steel
journal, September 2020

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

The Role of Co-injected Helium on Swelling and Cavity Evolution at High Damage Levels in Ferritic-Martensitic Steels
journal, July 2021

Low-temperature solubility of copper in iron: experimental study using thermoelectric power, small angle X-ray scattering and tomographic atom probe
journal, July 2005

Irradiation-induced Cu aggregations in Fe: An origin of embrittlement of reactor pressure vessel steels
journal, March 2001

Analysis of Three-dimensional Atom-probe Data by the Proximity Histogram
journal, September 2000

Radiation instability of equal channel angular extruded T91 at ultra-high damage levels
journal, June 2017

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

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

LAMDA: Irradiated-Materials Microscopy at Oak Ridge National Laboratory
journal, August 2015

Microstructural development in advanced ferritic–martensitic steel HCM12A
journal, June 2006

HT9 swelling in high burnup fast reactor fuel pin components
journal, June 2019

Additive manufacturing of steels: a review of achievements and challenges
journal, August 2020

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: Effect of temperature
journal, January 2020

Cladding and duct materials for advanced nuclear recycle reactors
journal, January 2008

Microstructure response of ferritic/martensitic steel HT9 after neutron irradiation: effect of dose
journal, September 2019

Dislocation Loops in Proton Irradiated Uranium-Nitrogen-Oxygen System
journal, December 2021

Direct Observation of Sink-Dependent Defect Evolution in Nanocrystalline Iron under Irradiation
journal, May 2017

CuMnNiSi precipitate evolution in irradiated reactor pressure vessel steels: Integrated Cluster Dynamics and experiments
journal, November 2019

Microstructure, Residual Strain and Stress Corrosion Cracking Behavior in 316L Heat-Affected Zone
journal, July 2016

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

Precipitate evolution in ion-irradiated HCM12A
journal, June 2012

Embrittlement of RPV steels: An atom probe tomography perspective
journal, September 2007

Vanadium diffusion coating on HT-9 cladding for mitigating the fuel cladding chemical interactions
journal, August 2014

Effects of 3d electron configurations on helium bubble formation and void swelling in concentrated solid-solution alloys
journal, December 2019

Radiation induced segregation and precipitation behavior in self-ion irradiated Ferritic/Martensitic HT9 steel
journal, August 2017

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

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

APT characterization of irradiated high nickel RPV steels
journal, April 2007

Radiation response of alloy T91 at damage levels up to 1000 peak dpa
journal, December 2016