Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments

Field, Kevin G.; Yang, Ying; Busby, Jeremy T.; Allen, Todd R.

doi:10.1016/j.actamat.2015.01.064

Title: Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments

Abstract

Radiation induced segregation (RIS) is a well-studied phenomena which occurs in many structurally relevant nuclear materials including austenitic stainless steels. RIS occurs due to solute atoms preferentially coupling to mobile point defect fluxes that migrate and interact with defect sinks. Here, a 304 stainless steel was neutron irradiated up to 47.1 dpa at 320 °C. Investigations into the RIS response at specific grain boundary types were utilized to determine the sink characteristics of different boundary types as a function of irradiation dose. A rate theory model built on the foundation of the modified inverse Kirkendall (MIK) model is proposed and benchmarked to the experimental results. This model, termed the GiMIK model, includes alterations in the boundary conditions based on grain boundary structure and includes expressions for interstitial binding. This investigation, through experiment and modeling, found specific grain boundary structures exhibit unique defect sink characteristics depending on their local structure. Furthermore, such interactions were found to be consistent across all doses investigated and had larger global implications including precipitation of Ni-Si clusters near different grain boundary types.

Authors:

Field, Kevin G. ^[1]; Yang, Ying ^[1]; Busby, Jeremy T. ^[1]; Allen, Todd R. ^[2]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: Mon Mar 09 00:00:00 EDT 2015

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Center for Nanophase Materials Sciences (CNMS)

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

OSTI Identifier:: 1185721

Alternate Identifier(s):: OSTI ID: 1255336

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Acta Materialia

Additional Journal Information:: Journal Volume: 89; Journal Issue: 1; Journal ID: ISSN 1359-6454

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE; RIS; sink strength; radiation tolerance; steel; grain boundary; irradiation; segregation; misorientation

Citation Formats


                    Field, Kevin G., Yang, Ying, Busby, Jeremy T., and Allen, Todd R. Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments.  United States: N. p., 2015. 
Web.  doi:10.1016/j.actamat.2015.01.064.

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                    Field, Kevin G., Yang, Ying, Busby, Jeremy T., & Allen, Todd R. Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments.  United States.  https://doi.org/10.1016/j.actamat.2015.01.064

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                    Field, Kevin G., Yang, Ying, Busby, Jeremy T., and Allen, Todd R. Mon .  
"Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments".  United States.  https://doi.org/10.1016/j.actamat.2015.01.064.  https://www.osti.gov/servlets/purl/1185721.

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@article{osti_1185721,

  title        = {Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments},

  author       = {Field, Kevin G. and Yang, Ying and Busby, Jeremy T. and Allen, Todd R.},

  abstractNote = {Radiation induced segregation (RIS) is a well-studied phenomena which occurs in many structurally relevant nuclear materials including austenitic stainless steels. RIS occurs due to solute atoms preferentially coupling to mobile point defect fluxes that migrate and interact with defect sinks. Here, a 304 stainless steel was neutron irradiated up to 47.1 dpa at 320 °C. Investigations into the RIS response at specific grain boundary types were utilized to determine the sink characteristics of different boundary types as a function of irradiation dose. A rate theory model built on the foundation of the modified inverse Kirkendall (MIK) model is proposed and benchmarked to the experimental results. This model, termed the GiMIK model, includes alterations in the boundary conditions based on grain boundary structure and includes expressions for interstitial binding. This investigation, through experiment and modeling, found specific grain boundary structures exhibit unique defect sink characteristics depending on their local structure. Furthermore, such interactions were found to be consistent across all doses investigated and had larger global implications including precipitation of Ni-Si clusters near different grain boundary types.},

  doi          = {10.1016/j.actamat.2015.01.064},

  journal      = {Acta Materialia},

  number       = 1,

  volume       = 89,

  place        = {United States},

  year         = {Mon Mar 09 00:00:00 EDT 2015},

  month        = {Mon Mar 09 00:00:00 EDT 2015}

}

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Works referencing / citing this record:

Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions
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Title: Defect sink characteristics of specific grain boundary types in 304 stainless steels under high dose neutron environments

Abstract

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Microstructural characterization of deformation localization at small strains in a neutron-irradiated 304 stainless steel journal, September 2014

Strain-induced phase transformation at the surface of an AISI-304 stainless steel irradiated to 4.4dpa and deformed to 0.8% strain journal, March 2014

Polycrystal orientation maps from TEM journal, August 2003

The structure of high-angle grain boundaries journal, November 1966

Modeling radiation-induced segregation in austenitic Fe–Cr–Ni alloys journal, June 1998

The effect of alloy composition on radiation-induced segregation in FeCrNi alloys journal, April 1997

Modeling solute-vacancy trapping at oversized solutes and its effect on radiation-induced segregation in Fe–Cr–Ni alloys journal, May 2009

The spatial resolution of X-ray microanalysis in the scanning transmission electron microscope journal, May 1980

A theory of radiation-induced segregation in concentrated alloys journal, August 1979

Dislocation loops at twin boundaries in an ion-irradiated austenitic alloy journal, October 1982

Irradiation creep mechanisms: An experimental perspective journal, October 1988

Elevated temperature irradiation hardening in austenitic stainless steel journal, July 1968

Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS journal, April 2003

Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels journal, February 2011

Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals journal, September 1999

Current understanding of radiation-induced degradation in light water reactor structural materials journal, March 2013

Modeling radiation induced segregation in Ni–Cr model alloys from first principles journal, June 2012

Measurement of grain-boundary segregation by STEM-EDX analysis journal, April 1989

Drift forces on vacancies and interstitials in alloys with radiation-induced segregation journal, February 1983

Point defect behaviour in irradiated materials journal, November 1975

Phase stability under irradiation journal, January 1984

Thermodynamic modeling and kinetics simulation of precipitate phases in AISI 316 stainless steels journal, May 2014

Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions journal, December 2015

Critical questions in materials science and engineering for successful development of fusion power
journal, August 2007

Structural materials for fission & fusion energy
journal, November 2009

Multimodal options for materials research to advance the basis for fusion energy in the ITER era
journal, September 2013

Role of atomic structure on grain boundary-defect interactions in Cu
journal, June 2012

Elimination of irradiation point defects in crystalline solids: Sink strengths
journal, April 2003

The effect of precipitate-matrix interface sinks on the growth of voids in the matrix
journal, January 1981

Effect of Grain Boundary Stresses on Sink Strength
journal, November 2013

Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels
journal, March 2013

Response of nanoclusters in a 9Cr ODS steel to 1dpa, 525°C proton irradiation
journal, December 2010

Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation
journal, March 2008

Influence of particle dispersions on the high-temperature strength of ferritic alloys
journal, August 2007

Effect of neutron irradiation on nanoclusters in MA957 ferritic alloys
journal, November 2011

Atom probe tomography of nanoscale particles in ODS ferritic alloys
journal, July 2003

Characterization of precipitates in MA/ODS ferritic alloys
journal, June 2006

Helium bubble distributions in a nanostructured ferritic alloy
journal, March 2013

Stability of nanometer-sized oxide clusters in mechanically-alloyed steel under ion-induced displacement cascade damage conditions
journal, February 2007

A review of refractory metal alloys and mechanically alloyed-oxide dispersion strengthened steels for space nuclear power systems
journal, April 2005

Recent results of the reduced activation ferritic/martensitic steel development
journal, August 2004

Effect of grain boundary character on sink efficiency
journal, October 2012

Grain boundary engineering for structure materials of nuclear reactors
journal, October 2013

Microstructure tailoring for property improvements by grain boundary engineering
journal, February 2008

Enhanced radiation tolerance in nanocrystalline MgGa2O4
journal, June 2007

Accumulation and recovery of defects in ion-irradiated nanocrystalline gold
journal, September 2001

Enhanced radiation tolerance of ultrafine grained Fe–Cr–Ni alloy
journal, January 2012

Anisotropic radiation-induced segregation in 316L austenitic stainless steel with grain boundary character
journal, April 2014

Solute segregation on Σ3 and random grain boundaries in type 316L stainless steel
journal, August 2013

Effect of grain boundary orientation on radiation-induced segregation in a Fe–15.2at.% Cr alloy
journal, May 2013

Effects of heavy-ion irradiation on the grain boundary chemistry of an oxide-dispersion strengthened Fe–12wt.% Cr alloy
journal, October 2011

A multi-scale approach to radiation-induced segregation at various grain boundaries
journal, August 2004

Effects of grain boundary misorientation on solute segregation in thermally sensitized and proton-irradiated 304 stainless steel
journal, December 2000

Dependence on grain boundary structure of radiation induced segregation in a 9wt.% Cr model ferritic/martensitic steel
journal, April 2013

Relationship between lath boundary structure and radiation induced segregation in a neutron irradiated 9wt.% Cr model ferritic/martensitic steel
journal, February 2014

Sink effect of grain boundary on radiation-induced segregation in austenitic stainless steel
journal, December 2000

Radiation-induced segregation and corrosion behavior on Σ3 coincidence site lattice and random grain boundaries in proton-irradiated type-316L austenitic stainless steel
journal, March 2013

Observation and rate theory modeling of grain boundary segregation in Σ3 twin boundaries in ion-irradiated stainless steel 316
journal, June 2014

Crack initiation behavior of neutron irradiated model and commercial stainless steels in high temperature water
journal, January 2014

Comparison of the microstructure, deformation and crack initiation behavior of austenitic stainless steel irradiated in-reactor or with protons
journal, January 2015

Alloying effect of Ni and Cr on irradiated microstructural evolution of type 304 stainless steels
journal, November 2013

Microstructural characterization of deformation localization at small strains in a neutron-irradiated 304 stainless steel
journal, September 2014

Strain-induced phase transformation at the surface of an AISI-304 stainless steel irradiated to 4.4dpa and deformed to 0.8% strain
journal, March 2014

Polycrystal orientation maps from TEM
journal, August 2003

The structure of high-angle grain boundaries
journal, November 1966

Modeling radiation-induced segregation in austenitic Fe–Cr–Ni alloys
journal, June 1998

The effect of alloy composition on radiation-induced segregation in FeCrNi alloys
journal, April 1997

Modeling solute-vacancy trapping at oversized solutes and its effect on radiation-induced segregation in Fe–Cr–Ni alloys
journal, May 2009

The spatial resolution of X-ray microanalysis in the scanning transmission electron microscope
journal, May 1980

A theory of radiation-induced segregation in concentrated alloys
journal, August 1979

Dislocation loops at twin boundaries in an ion-irradiated austenitic alloy
journal, October 1982

Irradiation creep mechanisms: An experimental perspective
journal, October 1988

Elevated temperature irradiation hardening in austenitic stainless steel
journal, July 1968

Influence of irradiation temperature and dose gradients on the microstructural evolution in neutron-irradiated 316SS
journal, April 2003

Novel features of radiation-induced segregation and radiation-induced precipitation in austenitic stainless steels
journal, February 2011

Radiation-induced material changes and susceptibility to intergranular failure of light-water-reactor core internals
journal, September 1999

Current understanding of radiation-induced degradation in light water reactor structural materials
journal, March 2013

Modeling radiation induced segregation in Ni–Cr model alloys from first principles
journal, June 2012

Measurement of grain-boundary segregation by STEM-EDX analysis
journal, April 1989

Drift forces on vacancies and interstitials in alloys with radiation-induced segregation
journal, February 1983

Point defect behaviour in irradiated materials
journal, November 1975

Phase stability under irradiation
journal, January 1984

Thermodynamic modeling and kinetics simulation of precipitate phases in AISI 316 stainless steels
journal, May 2014

Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions
journal, December 2015