Atom probe examinations of Zircaloy irradiated at nominally 358 °C

Cockeram, B. V.; Edmondson, P. D.; Leonard, K. J.; Kammenzind, B. F.; Hollenbeck, J. L.

doi:10.1016/j.nme.2019.03.023

Title: Atom probe examinations of Zircaloy irradiated at nominally 358 °C

Abstract

Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 10²⁴ n/m² (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing. Irradiation at the relatively high temperature of 358°C resulted in about 25–45% less hardening than observed in the literature for irradiations at 260–326°C. The lower irradiation hardening was shown to result from a coarser < a > loop distribution. The measured irradiation hardening was closely related to the ⟨a⟩ loop size and number density (ND) using an Orowan hardening model when the loops were assumed to be strong barriers like voids. In this work Atom Probe Tomography (APT) was used to detect the clustering of Fe, Sn, and Cr at features consistent with < a > loops. The tendency for clustering of Fe, Sn, and Cr at < a > loops could result in the apparent high barrier strength for these features. These clusters are also an additional hardening barrier. However, local variation in the distribution of clusters is observed from region to region in the irradiated material that appears to be related to factors such as the proximity to precipitates,more »« less

Authors:

Cockeram, B. V.;

; Leonard, K. J.; Kammenzind, B. F.; Hollenbeck, J. L.

Publication Date:: Wed May 01 00:00:00 EDT 2019

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

Sponsoring Org.:: USDOE Office of Science (SC)

OSTI Identifier:: 1529736

Alternate Identifier(s):: OSTI ID: 1558571

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Published Article

Journal Name:: Nuclear Materials and Energy

Additional Journal Information:: Journal Name: Nuclear Materials and Energy Journal Volume: 19 Journal Issue: C; Journal ID: ISSN 2352-1791

Publisher:: Elsevier

Country of Publication:: Netherlands

Language:: English

Subject:: 36 MATERIALS SCIENCE; Zircaloy; Irradiation Effects; Hardening; Clustering

Citation Formats


                    Cockeram, B. V., Edmondson, P. D., Leonard, K. J., Kammenzind, B. F., and Hollenbeck, J. L. Atom probe examinations of Zircaloy irradiated at nominally 358 °C.  Netherlands: N. p., 2019. 
Web.  doi:10.1016/j.nme.2019.03.023.

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                    Cockeram, B. V., Edmondson, P. D., Leonard, K. J., Kammenzind, B. F., & Hollenbeck, J. L. Atom probe examinations of Zircaloy irradiated at nominally 358 °C.  Netherlands.  https://doi.org/10.1016/j.nme.2019.03.023

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                    Cockeram, B. V., Edmondson, P. D., Leonard, K. J., Kammenzind, B. F., and Hollenbeck, J. L. Wed .  
"Atom probe examinations of Zircaloy irradiated at nominally 358 °C".  Netherlands.  https://doi.org/10.1016/j.nme.2019.03.023.

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@article{osti_1529736,

  title        = {Atom probe examinations of Zircaloy irradiated at nominally 358 °C},

  author       = {Cockeram, B. V. and Edmondson, P. D. and Leonard, K. J. and Kammenzind, B. F. and Hollenbeck, J. L.},

  abstractNote = {Zircaloy-2 and Zircaloy-4 were neutron irradiated at 358 °C in the high flux isotope reactor (HFIR) to a neutron fluence of 29.6 × 1024 n/m2 (E > 1 MeV) and the resultant irradiation hardening was measured by tensile testing. Irradiation at the relatively high temperature of 358°C resulted in about 25–45% less hardening than observed in the literature for irradiations at 260–326°C. The lower irradiation hardening was shown to result from a coarser < a > loop distribution. The measured irradiation hardening was closely related to the ⟨a⟩ loop size and number density (ND) using an Orowan hardening model when the loops were assumed to be strong barriers like voids. In this work Atom Probe Tomography (APT) was used to detect the clustering of Fe, Sn, and Cr at features consistent with < a > loops. The tendency for clustering of Fe, Sn, and Cr at < a > loops could result in the apparent high barrier strength for these features. These clusters are also an additional hardening barrier. However, local variation in the distribution of clusters is observed from region to region in the irradiated material that appears to be related to factors such as the proximity to precipitates, local variations in microstructure, and/or microchemistry.},

  doi          = {10.1016/j.nme.2019.03.023},

  journal      = {Nuclear Materials and Energy},

  number       = C,

  volume       = 19,

  place        = {Netherlands},

  year         = {Wed May 01 00:00:00 EDT 2019},

  month        = {Wed May 01 00:00:00 EDT 2019}

}

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Similar Records

Title: Atom probe examinations of Zircaloy irradiated at nominally 358 °C

Abstract

Citation Formats

The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C journal, June 2015

A ballistic mixing model for the amorphization of precipitates in Zircaloy under neutron irradiation journal, November 1992

Evolution of microstructure in hcp metals during irradiation journal, October 1993

Analysis of atomic distribution in as-fabricated Zircaloy-2 claddings by atom probe tomography under high-energy pulsed laser journal, November 2013

Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C journal, June 2014

Methods of quantitative matrix analysis of Zircaloy-2 journal, May 2011

Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress journal, January 2008

Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure journal, November 2014

The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr journal, January 2016

Spinodal decomposition of Ti0.33Al0.67N thin films studied by atom probe tomography journal, April 2012

The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy journal, May 2017

Atom probe tomography study of alloying element distributions in Zr alloys and their oxides journal, November 2013

Defect clusters in neutron-irradiated vanadium containing oxygen journal, March 1976

A statistical TEM investigation of dislocation channeling mechanism in neutron irradiated zirconium alloys journal, July 2004

Quantitative atom probe tomography characterization of microstructures in a proton irradiated 304 stainless steel journal, August 2014

The use of a laser-assisted Local Electrode Atom Probe and TEM to examine the microstructure of Zircaloy and precipitate structure following low dose neutron irradiation at nominally 358°C journal, February 2013

Optimisation of mass ranging for atom probe microanalysis and application to the corrosion processes in Zr alloys journal, May 2011

Comments on precipitate stability in neutron-irradiated Zircaloy-4 journal, March 1990

Studies of dislocations by field ion microscopy and atom probe tomography journal, September 2013

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Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 358°C journal, November 2011

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Atom probe specimen preparation with a dual beam SEM/FIB miller journal, September 2007

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

Microstructural changes during thermally induced strain recovery in irradiated zircaloy-4 stress relaxation specimens journal, February 1977

Effects of microchemistry and precipitate size on nodular corrosion resistance of Zircaloy-2 journal, July 1992

Atom probe crystallography journal, September 2012

Characterization of neutron irradiation damage in zirconium alloys — an international “round-robin” experiment journal, February 1979

Title: Atom probe examinations of Zircaloy irradiated at nominally 358 °C

The recovery of irradiation damage for Zircaloy-2 and Zircaloy-4 following low dose neutron irradiation at nominally 358 °C
journal, June 2015

A ballistic mixing model for the amorphization of precipitates in Zircaloy under neutron irradiation
journal, November 1992

Evolution of microstructure in hcp metals during irradiation
journal, October 1993

Analysis of atomic distribution in as-fabricated Zircaloy-2 claddings by atom probe tomography under high-energy pulsed laser
journal, November 2013

Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 377–440°C
journal, June 2014

Methods of quantitative matrix analysis of Zircaloy-2
journal, May 2011

Experimental and Modeling Approach of Irradiation Defects Recovery in Zirconium Alloys: Impact of an Applied Stress
journal, January 2008

Redistribution of alloying elements in Zircaloy-2 after in-reactor exposure
journal, November 2014

The effect of crystallographic mismatch on the obstacle strength of second phase precipitate particles in dispersion strengthening: bcc Nb particles and nanometric Nb clusters embedded in hcp Zr
journal, January 2016

Spinodal decomposition of Ti0.33Al0.67N thin films studied by atom probe tomography
journal, April 2012

The effect of matrix chemistry on dislocation evolution in an irradiated Zr alloy
journal, May 2017

Atom probe tomography study of alloying element distributions in Zr alloys and their oxides
journal, November 2013

Defect clusters in neutron-irradiated vanadium containing oxygen
journal, March 1976

A statistical TEM investigation of dislocation channeling mechanism in neutron irradiated zirconium alloys
journal, July 2004

Quantitative atom probe tomography characterization of microstructures in a proton irradiated 304 stainless steel
journal, August 2014

The use of a laser-assisted Local Electrode Atom Probe and TEM to examine the microstructure of Zircaloy and precipitate structure following low dose neutron irradiation at nominally 358°C
journal, February 2013

Optimisation of mass ranging for atom probe microanalysis and application to the corrosion processes in Zr alloys
journal, May 2011

Comments on precipitate stability in neutron-irradiated Zircaloy-4
journal, March 1990

Studies of dislocations by field ion microscopy and atom probe tomography
journal, September 2013

How the crystallography and nanoscale chemistry of the metal/oxide interface develops during the aqueous oxidation of zirconium cladding alloys
journal, December 2012

Development of microstructure and irradiation hardening of Zircaloy during low dose neutron irradiation at nominally 358°C
journal, November 2011

Nano-scale chemical evolution in a proton-and neutron-irradiated Zr alloy
journal, April 2017

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

Correlated ion analysis and the interpretation of atom probe mass spectra
journal, May 2011

From solid solution to cluster formation of Fe and Cr in α -Zr
journal, December 2015

Initial observation of grain boundary solute segregation in a zirconium alloy (ZIRLO) by three-dimensional atom probe
journal, August 2009

Zirconium oxidation on the atomic scale
journal, April 2009

Atom probe specimen preparation with a dual beam SEM/FIB miller
journal, September 2007

A sensitivity analysis of the maximum separation method for the characterisation of solute clusters
journal, May 2011

Phase instability, decomposition and redistribution of intermetallic precipitates in Zircaloy-2 and -4 during neutron irradiation
journal, September 1987

Grain boundary sinks in neutron-irradiated Zr and Zr-alloys
journal, October 1988

Microstructure evolution in h.c.p. metals during irradiation
journal, May 1991

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

Microstructural changes during thermally induced strain recovery in irradiated zircaloy-4 stress relaxation specimens
journal, February 1977

Effects of microchemistry and precipitate size on nodular corrosion resistance of Zircaloy-2
journal, July 1992

Atom probe crystallography
journal, September 2012

Characterization of neutron irradiation damage in zirconium alloys — an international “round-robin” experiment
journal, February 1979