Lattice Strain Mapping of Cracks and Indentations in UO2 using Synchrotron Microdiffraction

Mo, Kun; Miao, Yinbin; Xu, Ruqing; Yao, Tiankai; Lian, Jie; Jamison, Laura M.; Yacout, Abdellatif M.

doi:10.1016/j.jnucmat.2019.151943

Title: Lattice Strain Mapping of Cracks and Indentations in UO₂ using Synchrotron Microdiffraction

Abstract

Fractures and cracks commonly found in UO₂ fuel in nuclear reactors have been studied for decades. In this study, an advanced synchrotron micro X-ray diffraction (XRD) technique was used to study lattice strain development in cracking and indentation regions of micro-indented UO₂ materials. A stoichiometric UO₂ sample prepared by spark plasma sintering (SPS) was indented with a microscale Vickers indenter. The cracks and other defects on the sample surface observed in scanning electron microscope were correlated to the micro-diffraction measurements by Laue diffraction signal intensities, so that the lattice strains developed in those microstructures could be precisely mapped. We report the highest and lowest strained areas were found near the indentation tip and within the "open" crack, respectively. Induced by the residual stress, the lattice strain near the indentation was found to progressively decrease radially from the indentation boundary.

Authors:

Mo, Kun ^[1]; Miao, Yinbin ^[1]; Xu, Ruqing ^[1]; Yao, Tiankai ^[2]; Lian, Jie ^[3]; Jamison, Laura M. ^[1]; Yacout, Abdellatif M. ^[1]

Argonne National Lab. (ANL), Lemont, IL (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States); Rensselaer Polytechnic Inst., Troy, NY (United States)
Rensselaer Polytechnic Inst., Troy, NY (United States)

Publication Date:: Wed Dec 04 00:00:00 EST 2019

Research Org.:: Argonne National Lab. (ANL), Argonne, IL (United States). Advanced Photon Source (APS)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE), Nuclear Energy University Program (NEUP); USDOE Office of Nuclear Energy (NE), Nuclear Energy Advanced Modeling and Simulation (NEAMS); USDOE

OSTI Identifier:: 1606403

Alternate Identifier(s):: OSTI ID: 1693659

Grant/Contract Number:: AC02-06CH11357; NE0008564; AC-02-06CH11357

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 529; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; Micro-diffraction; Synchrotron radiation; Uranium oxide; Strain; Residual stress

Citation Formats


                    Mo, Kun, Miao, Yinbin, Xu, Ruqing, Yao, Tiankai, Lian, Jie, Jamison, Laura M., and Yacout, Abdellatif M. Lattice Strain Mapping of Cracks and Indentations in UO2 using Synchrotron Microdiffraction.  United States: N. p., 2019. 
Web.  doi:10.1016/j.jnucmat.2019.151943.

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                    Mo, Kun, Miao, Yinbin, Xu, Ruqing, Yao, Tiankai, Lian, Jie, Jamison, Laura M., & Yacout, Abdellatif M. Lattice Strain Mapping of Cracks and Indentations in UO2 using Synchrotron Microdiffraction.  United States.  https://doi.org/10.1016/j.jnucmat.2019.151943

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                    Mo, Kun, Miao, Yinbin, Xu, Ruqing, Yao, Tiankai, Lian, Jie, Jamison, Laura M., and Yacout, Abdellatif M. Wed .  
"Lattice Strain Mapping of Cracks and Indentations in UO2 using Synchrotron Microdiffraction".  United States.  https://doi.org/10.1016/j.jnucmat.2019.151943.  https://www.osti.gov/servlets/purl/1606403.

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@article{osti_1606403,

  title        = {Lattice Strain Mapping of Cracks and Indentations in UO2 using Synchrotron Microdiffraction},

  author       = {Mo, Kun and Miao, Yinbin and Xu, Ruqing and Yao, Tiankai and Lian, Jie and Jamison, Laura M. and Yacout, Abdellatif M.},

  abstractNote = {Fractures and cracks commonly found in UO2 fuel in nuclear reactors have been studied for decades. In this study, an advanced synchrotron micro X-ray diffraction (XRD) technique was used to study lattice strain development in cracking and indentation regions of micro-indented UO2 materials. A stoichiometric UO2 sample prepared by spark plasma sintering (SPS) was indented with a microscale Vickers indenter. The cracks and other defects on the sample surface observed in scanning electron microscope were correlated to the micro-diffraction measurements by Laue diffraction signal intensities, so that the lattice strains developed in those microstructures could be precisely mapped. We report the highest and lowest strained areas were found near the indentation tip and within the "open" crack, respectively. Induced by the residual stress, the lattice strain near the indentation was found to progressively decrease radially from the indentation boundary.},

  doi          = {10.1016/j.jnucmat.2019.151943},

  journal      = {Journal of Nuclear Materials},

  number       = ,

  volume       = 529,

  place        = {United States},

  year         = {Wed Dec 04 00:00:00 EST 2019},

  month        = {Wed Dec 04 00:00:00 EST 2019}

}

Copy to clipboard

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Works referenced in this record:

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Title: Lattice Strain Mapping of Cracks and Indentations in UO2 using Synchrotron Microdiffraction

Abstract

Citation Formats

Uranium dioxide properties for LWR fuel rods journal, September 1975

Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry journal, April 2019

The strength and fracture of stoichiometric polycrystalline UO2 journal, December 1969

Deformation of UO2 at High Temperatures journal, February 1971

The room temperature fracture strength of sintered UO2 rings containing deliberately introduced impurities journal, April 1976

Fracture stress and elastic modulus of uranium dioxide including excess oxygen journal, January 1973

Effect of Temperature and Deformation Rate on Fracture Strength of Sintered Uranium Dioxide journal, April 1979

Overview no. 5 journal, October 1979

The surface energy of UO2 as determined by hertzian indentation journal, June 1980

Microstructure Effects on Fracture Strength of U0 2 Fuel Pellets journal, December 1982

Fracture toughness and fracture surface energy of sintered uranium dioxide fuel pellets journal, March 1987

Fracture properties of sintered UO2 ceramic pellets with duplex microstructure journal, June 2007

A continuum model for cracked UO2 fuel journal, November 1997

Oxide fuel transients journal, July 1989

The development of grain-face porosity in irradiated oxide fuel journal, February 2004

Concerning the development of grain face bubbles and fission gas release in UO2 fuel journal, November 1988

Percolation on grain boundary networks: Application to fission gas release in nuclear fuels journal, February 2012

On the Pellet-Cladding Interaction Phenomenon journal, August 1977

Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review journal, August 1990

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Room-temperature microindentation behaviour of LWR-fuels, part 1: fuel microhardness journal, November 2003

Crack tip plasticity in single crystal UO2: Atomistic simulations journal, November 2012

Molecular dynamics simulations of intergranular fracture in UO2 with nine empirical interatomic potentials journal, September 2014

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Characterization of high energy Xe ion irradiation effects in single crystal molybdenum with depth-resolved synchrotron microbeam diffraction journal, April 2016

Correlation between crystallographic orientation and surface faceting in UO2 journal, September 2016

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Three-dimensional X-ray structural microscopy with submicrometre resolution journal, February 2002

Nondestructive three-dimensional characterization of grain boundaries by X-ray crystal microscopy journal, June 2005

Dislocation Density Tensor Characterization of Deformation Using 3D X-Ray Microscopy journal, April 2008

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Investigation of the oxygen activity of oxide fuels and fuel-fission product systems by solid electrolyte techniques. Part I: Qualification and limitations of the method journal, June 1983

Study of irradiated mod.9Cr–1Mo steel by synchrotron extended X-ray absorption fine structure journal, October 2013

In situ synchrotron investigation of grain growth behavior of nano-grained UO 2 journal, April 2017

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Characterization of neutron-irradiated HT-UPS steel by high-energy X-ray diffraction microscopy journal, April 2016

In situ high-energy X-ray diffraction study of tensile deformation of neutron-irradiated polycrystalline Fe-9%Cr alloy journal, March 2017

i RadMat: A thermo-mechanical testing system for in situ high-energy X-ray characterization of radioactive specimens journal, January 2017

High-energy x-ray diffraction microscopy study of deformation microstructures in neutron-irradiated polycrystalline Fe-9%Cr journal, September 2018

In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation journal, September 2018

Review on Numerical Modeling of Instrumented Indentation Tests for Elastoplastic Material Behavior Identification journal, September 2014

Study of the concept of representative strain and constraint factor introduced by Vickers indentation journal, January 2014

Comparison between Berkovich, Vickers and conical indentation tests: A three-dimensional numerical simulation study journal, March 2009

Three-dimensional numerical simulation of Vickers indentation tests journal, February 2006

Full elastic strain and stress tensor measurements from individual dislocation cells in copper through-Si vias journal, September 2015

Lattice swelling and modulus change in a helium-implanted tungsten alloy: X-ray micro-diffraction, surface acoustic wave measurements, and multiscale modelling journal, May 2015

Title: Lattice Strain Mapping of Cracks and Indentations in UO₂ using Synchrotron Microdiffraction

Uranium dioxide properties for LWR fuel rods
journal, September 1975

Nano- and micro-indentation testing of sintered UO2 fuel pellets with controlled microstructure and stoichiometry
journal, April 2019

The strength and fracture of stoichiometric polycrystalline UO2
journal, December 1969

Deformation of UO2 at High Temperatures
journal, February 1971

The room temperature fracture strength of sintered UO2 rings containing deliberately introduced impurities
journal, April 1976

Fracture stress and elastic modulus of uranium dioxide including excess oxygen
journal, January 1973

Effect of Temperature and Deformation Rate on Fracture Strength of Sintered Uranium Dioxide
journal, April 1979

Overview no. 5
journal, October 1979

The surface energy of UO2 as determined by hertzian indentation
journal, June 1980

Microstructure Effects on Fracture Strength of U0 ² Fuel Pellets
journal, December 1982

Fracture toughness and fracture surface energy of sintered uranium dioxide fuel pellets
journal, March 1987

Fracture properties of sintered UO2 ceramic pellets with duplex microstructure
journal, June 2007

A continuum model for cracked UO2 fuel
journal, November 1997

Oxide fuel transients
journal, July 1989

The development of grain-face porosity in irradiated oxide fuel
journal, February 2004

Concerning the development of grain face bubbles and fission gas release in UO2 fuel
journal, November 1988

Percolation on grain boundary networks: Application to fission gas release in nuclear fuels
journal, February 2012

On the Pellet-Cladding Interaction Phenomenon
journal, August 1977

Pellet-clad interaction (PCI) failures of zirconium alloy fuel cladding — A review
journal, August 1990

Effect of titania addition on hot hardness of UO2
journal, February 2004

Room-temperature microindentation behaviour of LWR-fuels, part 1: fuel microhardness
journal, November 2003

Crack tip plasticity in single crystal UO2: Atomistic simulations
journal, November 2012

Molecular dynamics simulations of intergranular fracture in UO2 with nine empirical interatomic potentials
journal, September 2014

An object-oriented finite element framework for multiphysics phase field simulations
journal, January 2012

In situ TEM and synchrotron characterization of U–10Mo thin specimen annealed at the fast reactor temperature regime
journal, December 2015

Characterization of high energy Xe ion irradiation effects in single crystal molybdenum with depth-resolved synchrotron microbeam diffraction
journal, April 2016

Correlation between crystallographic orientation and surface faceting in UO2
journal, September 2016

Phase decomposition and bubble evolution in Xe implanted U3Si2 at 450∘C
journal, May 2019

Three-dimensional X-ray structural microscopy with submicrometre resolution
journal, February 2002

Nondestructive three-dimensional characterization of grain boundaries by X-ray crystal microscopy
journal, June 2005

Dislocation Density Tensor Characterization of Deformation Using 3D X-Ray Microscopy
journal, April 2008

TiO2 doped UO2 fuels sintered by spark plasma sintering
journal, February 2016

Grain growth and pore coarsening in dense nano‐crystalline UO _{2+ x} fuel pellets
journal, March 2017

Investigation of the oxygen activity of oxide fuels and fuel-fission product systems by solid electrolyte techniques. Part I: Qualification and limitations of the method
journal, June 1983

Study of irradiated mod.9Cr–1Mo steel by synchrotron extended X-ray absorption fine structure
journal, October 2013

In situ synchrotron investigation of grain growth behavior of nano-grained UO 2
journal, April 2017

High-energy synchrotron study of in-pile-irradiated U–Mo fuels
journal, March 2016

Characterization of neutron-irradiated HT-UPS steel by high-energy X-ray diffraction microscopy
journal, April 2016

In situ high-energy X-ray diffraction study of tensile deformation of neutron-irradiated polycrystalline Fe-9%Cr alloy
journal, March 2017

i RadMat: A thermo-mechanical testing system for in situ high-energy X-ray characterization of radioactive specimens
journal, January 2017

High-energy x-ray diffraction microscopy study of deformation microstructures in neutron-irradiated polycrystalline Fe-9%Cr
journal, September 2018

In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation
journal, September 2018

Review on Numerical Modeling of Instrumented Indentation Tests for Elastoplastic Material Behavior Identification
journal, September 2014

Study of the concept of representative strain and constraint factor introduced by Vickers indentation
journal, January 2014

Comparison between Berkovich, Vickers and conical indentation tests: A three-dimensional numerical simulation study
journal, March 2009

Three-dimensional numerical simulation of Vickers indentation tests
journal, February 2006

Full elastic strain and stress tensor measurements from individual dislocation cells in copper through-Si vias
journal, September 2015

Lattice swelling and modulus change in a helium-implanted tungsten alloy: X-ray micro-diffraction, surface acoustic wave measurements, and multiscale modelling
journal, May 2015