Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy

Auger, Maria A.; Hoelzer, David T.; Field, Kevin G.; Moody, Michael P.

doi:10.1016/j.jnucmat.2019.151852

Title: Nanoscale analysis of ion irradiated ODS 14YWT ferritic alloy

Journal Article · 21 October 2019 · Journal of Nuclear Materials

DOI: https://doi.org/10.1016/j.jnucmat.2019.151852 · OSTI ID:1607192

Auger, Maria A. ^[1];

^[2];

^[2]; Moody, Michael P. ^[3]

Univ. Carlos III de Madrid (Spain); Univ. of Oxford (United Kingdom)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Univ. of Oxford (United Kingdom)

In this work, the nanoscale microstructure of an advanced oxide dispersion strengthened (ODS) 14YWT ferritic alloy (SM13 heat) with nominal composition Fe–14Cr–3W-0.4Ti-0.3Y₂O₃ (wt. %) has been characterized by atom probe tomography (APT) before and after ion irradiation with 70 MeV Fe⁹⁺ ions at 450 °C to a total dose of 21 dpa. A detailed solute cluster analysis of APT data reveals that, in the manufacturing process, larger nanoparticles form in or close to the grain boundaries respective to those inside grains. The evolution of the nanoparticles after irradiation seems to be related to their location, as a higher increase in the number density and in the Y:Ti ratio is observed for the nanoparticles in or close to grain boundaries. Furthermore, APT analysis also shows Cr, W and C segregation to grain boundaries enhanced by the irradiation. A previous study of this same alloy before and after irradiation reports that the mechanical properties do not seem to be affected, but the microstructure was not investigated to confirm. The present work confirms little microstructural evolution after irradiation in this 14YWT alloy, indicating tolerance at the given irradiation conditions.

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

Sponsoring Organization:: Engineering and Physical Sciences Research Council (EPSRC); USDOE Office of Nuclear Energy (NE). Nuclear Energy University Program (NEUP); Comunidad Autonoma de Madrid-Spain; Henry Royce Institute for Advanced Materials

Grant/Contract Number:: AC05-00OR22725; NE0000639; EP/P001645/1; EP/L025817/1; EP/M022803/1

OSTI ID:: 1607192

Alternate ID(s):: OSTI ID: 1577898

Journal Information:: Journal of Nuclear Materials, Vol. 528, Issue C; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

References (36)

Perspective of ODS alloys application in nuclear environments Ukai, Shigeharu; Fujiwara, Masayuki Journal of Nuclear Materials, Vol. 307-311, p. 749-757 https://doi.org/10.1016/S0022-3115(02)01043-7	journal	December 2002
Materials needs for fusion, Generation IV fission reactors and spallation neutron sources – similarities and differences Mansur, L. K.; Rowcliffe, A. F.; Nanstad, R. K. Journal of Nuclear Materials, Vol. 329-333 https://doi.org/10.1016/j.jnucmat.2004.04.016	journal	August 2004
Recent Developments in Irradiation-Resistant Steels Odette, G. R.; Alinger, M. J.; Wirth, B. D. Annual Review of Materials Research, Vol. 38, Issue 1, p. 471-503 https://doi.org/10.1146/annurev.matsci.38.060407.130315	journal	August 2008
Optimization of the chemical composition and manufacturing route for ODS RAF steels for fusion reactor application Oksiuta, Z.; Baluc, N. Nuclear Fusion, Vol. 49, Issue 5 https://doi.org/10.1088/0029-5515/49/5/055003	journal	April 2009
Structural materials for fission & fusion energy Zinkle, Steven J.; Busby, Jeremy T. Materials Today, Vol. 12, Issue 11 https://doi.org/10.1016/S1369-7021(09)70294-9	journal	November 2009
Atomic structure of nanoclusters in oxide-dispersion-strengthened steels Hirata, A.; Fujita, T.; Wen, Y. R. Nature Materials, Vol. 10, Issue 12, p. 922-926 https://doi.org/10.1038/nmat3150	journal	October 2011
Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications Zinkle, S. J.; Boutard, J. L.; Hoelzer, D. T. Nuclear Fusion, Vol. 57, Issue 9 https://doi.org/10.1088/1741-4326/57/9/092005	journal	June 2017
Operating temperature windows for fusion reactor structural materials Zinkle, S. J.; Ghoniem, N. M. Fusion Engineering and Design, Vol. 51-52, p. 55-71 https://doi.org/10.1016/S0920-3796(00)00320-3	journal	November 2000
A review of the irradiation evolution of dispersed oxide nanoparticles in the b.c.c. Fe-Cr system: Current understanding and future directions Wharry, Janelle P.; Swenson, Matthew J.; Yano, Kayla H. Journal of Nuclear Materials, Vol. 486 https://doi.org/10.1016/j.jnucmat.2017.01.009	journal	April 2017
Mechanical properties of irradiated ODS-EUROFER and nanocluster strengthened 14YWT McClintock, D. A.; Sokolov, M. A.; Hoelzer, D. T. Journal of Nuclear Materials, Vol. 392, Issue 2 https://doi.org/10.1016/j.jnucmat.2009.03.024	journal	July 2009
Radiation stability of nanoclusters in nano-structured oxide dispersion strengthened (ODS) steels Certain, A.; Kuchibhatla, S.; Shutthanandan, V. Journal of Nuclear Materials, Vol. 434, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2012.11.021	journal	March 2013
Characterisation of ODS Fe-14Cr-2W-0.3Ti before and after high temperature triple and low temperature single ion irradiations Šćepanović, M.; Leguey, T.; Auger, M. A. Materials Characterization, Vol. 136 https://doi.org/10.1016/j.matchar.2017.12.025	journal	February 2018
Effect of grain boundary orientation on radiation-induced segregation in a Fe–15.2at.% Cr alloy Hu, Rong; Smith, George D. W.; Marquis, Emmanuelle A. Acta Materialia, Vol. 61, Issue 9 https://doi.org/10.1016/j.actamat.2013.02.043	journal	May 2013
Response of nanostructured ferritic alloys to high-dose heavy ion irradiation Parish, Chad M.; White, Ryan M.; LeBeau, James M. Journal of Nuclear Materials, Vol. 445, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2013.11.002	journal	February 2014
Radiation tolerance of commercial and advanced alloys for core internals: a comprehensive microstructural characterization Song, Miao; Lear, Calvin R.; Parish, Chad M. Journal of Nuclear Materials, Vol. 510 https://doi.org/10.1016/j.jnucmat.2018.08.035	journal	November 2018
Micro mechanical testing of candidate structural alloys for Gen-IV nuclear reactors Prasitthipayong, A.; Frazer, D.; Kareer, A. Nuclear Materials and Energy, Vol. 16 https://doi.org/10.1016/j.nme.2018.05.018	journal	August 2018
SRIM – The stopping and range of ions in matter (2010) Ziegler, James F.; Ziegler, M. D.; Biersack, J. P. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 268, Issue 11-12 https://doi.org/10.1016/j.nimb.2010.02.091	journal	June 2010
Review of Atom Probe FIB-Based Specimen Preparation Methods Miller, Michael K.; Russell, Kaye F.; Thompson, Keith Microscopy and Microanalysis, Vol. 13, Issue 6 https://doi.org/10.1017/S1431927607070845	journal	November 2007
Defining clusters in APT reconstructions of ODS steels Williams, Ceri A.; Haley, Daniel; Marquis, Emmanuelle A. Ultramicroscopy, Vol. 132 https://doi.org/10.1016/j.ultramic.2012.12.011	journal	September 2013
Atom Probe Tomography: A Technique for Nanoscale Characterization Miller, M. K.; Kenik, E. A. Microscopy and Microanalysis, Vol. 10, Issue 3 https://doi.org/10.1017/S1431927604040577	journal	June 2004
The stability of precipitates in an irradiation environment Nelson, R. S.; Hudson, J. A.; Mazey, D. J. Journal of Nuclear Materials, Vol. 44, Issue 3 https://doi.org/10.1016/0022-3115(72)90043-8	journal	September 1972
Analytical characterization of secondary phases and void distributions in an ultrafine-grained ODS Fe–14Cr model alloy de Castro, V.; Leguey, T.; Auger, M. A. Journal of Nuclear Materials, Vol. 417, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.067	journal	October 2011
Effect of the milling atmosphere on the microstructure and mechanical properties of a ODS Fe-14Cr model alloy Auger, M. A.; de Castro, V.; Leguey, T. Materials Science and Engineering: A, Vol. 671 https://doi.org/10.1016/j.msea.2016.06.054	journal	August 2016
Response of 9Cr-ODS steel to proton irradiation at 400°C He, Jianchao; Wan, Farong; Sridharan, Kumar Journal of Nuclear Materials, Vol. 452, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.05.004	journal	September 2014
Stability of nanoclusters in 14YWT oxide dispersion strengthened steel under heavy ion-irradiation by atom probe tomography He, Jianchao; Wan, Farong; Sridharan, Kumar Journal of Nuclear Materials, Vol. 455, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2014.03.024	journal	December 2014
The comparison of microstructure and nanocluster evolution in proton and neutron irradiated Fe–9%Cr ODS steel to 3 dpa at 500 °C Swenson, M. J.; Wharry, J. P. Journal of Nuclear Materials, Vol. 467 https://doi.org/10.1016/j.jnucmat.2015.09.022	journal	December 2015
Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys Was, Gary S.; Wharry, Janelle P.; Frisbie, Brian Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2011.01.031	journal	April 2011
Segregation behavior in proton- and heavy-ion-irradiated ferritic–martensitic alloys Jiao, Z.; Was, G. S. Acta Materialia, Vol. 59, Issue 11 https://doi.org/10.1016/j.actamat.2011.03.070	journal	June 2011
Effects of single- and simultaneous triple-ion-beam irradiation on an oxide dispersion-strengthened Fe12Cr steel de Castro, Vanessa; Lozano-Perez, Sergio; Briceno, Martha Journal of Materials Science, Vol. 50, Issue 5 https://doi.org/10.1007/s10853-014-8794-y	journal	December 2014
Influences of interstitial and extrusion temperature on grain boundary segregation, Y−Ti−O nanofeatures, and mechanical properties of ferritic steels Seol, Jae Bok; Haley, Daniel; Hoelzer, David T. Acta Materialia, Vol. 153 https://doi.org/10.1016/j.actamat.2018.04.046	journal	July 2018
Radiation response of a 9 chromium oxide dispersion strengthened steel to heavy ion irradiation Allen, T. R.; Gan, J.; Cole, J. I. Journal of Nuclear Materials, Vol. 375, Issue 1 https://doi.org/10.1016/j.jnucmat.2007.11.001	journal	March 2008
Ab-initio based modeling of diffusion in dilute bcc Fe–Ni and Fe–Cr alloys and implications for radiation induced segregation Choudhury, S.; Barnard, L.; Tucker, J. D. Journal of Nuclear Materials, Vol. 411, Issue 1-3 https://doi.org/10.1016/j.jnucmat.2010.12.231	journal	April 2011
Characterization of microstructure and property evolution in advanced cladding and duct: Materials exposed to high dose and elevated temperature Allen, Todd R.; Kaoumi, Djamel; Wharry, Janelle P. Journal of Materials Research, Vol. 30, Issue 9 https://doi.org/10.1557/jmr.2015.99	journal	May 2015
Correlation of in-situ transmission electron microscopy and microchemistry analysis of radiation-induced precipitation and segregation in ion irradiated advanced ferritic/martensitic steels Zheng, Ce; Ke, Jia-Hong; Maloy, Stuart A. Scripta Materialia, Vol. 162 https://doi.org/10.1016/j.scriptamat.2018.12.018	journal	March 2019
Resolution of the carbon contamination problem in ion irradiation experiments Was, G. S.; Taller, S.; Jiao, Z. Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms, Vol. 412 https://doi.org/10.1016/j.nimb.2017.08.039	journal	December 2017
Influence of processing on the microstructure and mechanical properties of 14YWT Hoelzer, D. T.; Unocic, K. A.; Sokolov, M. A. Journal of Nuclear Materials, Vol. 471 https://doi.org/10.1016/j.jnucmat.2015.12.011	journal	April 2016