Microstructure evolution of T91 irradiated in the BOR60 fast reactor

Jiao, Z.; Taller, S.; Field, K.; Yeli, G.; Moody, M. P.; Was, G. S.

doi:10.1016/j.jnucmat.2018.03.024

Title: Microstructure evolution of T91 irradiated in the BOR60 fast reactor

Abstract

In this paper, microstructures of T91 neutron irradiated in the BOR60 reactor at five temperatures between 376 °C and 524 °C to doses between 15.4 and 35.1 dpa were characterized using transmission electron microscopy (TEM), scanning transmission electron microscopy (STEM), and atom probe tomography (APT). Type a<100> dislocation loops were observed at 376–415 °C and network dislocations dominated at 460 °C and 524 °C. Cavities appeared in a bimodal distribution with a high density of small bubbles less than 2 nm at irradiation temperatures between 376 °C and 415 °C. Small bubbles were also observed at 460 °C and 524 °C but cavities greater than 2 nm were absent. Enrichment of Cr, Ni, and Si at the grain boundary was observed at all irradiation temperatures. Radiation-induced segregation (RIS) of Cr, Ni and Si appeared to saturate at 17.1 dpa and 376 °C. The temperature dependence of RIS of Cr, Ni and Si at the grain boundary, which showed a peak Cr enrichment temperature of 460 °C and a lower peak Ni and Si enrichment temperature of ~400 °C, was consistent with observations of RIS of Cr in proton irradiated T91, suggesting that the same RIS mechanism may also apply tomore »« less

Authors:

Jiao, Z. ^[1]; Taller, S. ^[1];

^[2]; Yeli, G. ^[3]; Moody, M. P. ^[3]; Was, G. S. ^[1]

Univ. of Michigan, Ann Arbor, MI (United States). Dept. of Nuclear Engineering and Radiological Sciences
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science & Technology Division
Univ. of Oxford (United Kingdom). Dept. of Materials

Publication Date:: Wed Mar 14 00:00:00 EDT 2018

Research Org.:: Univ. of Michigan, Ann Arbor, MI (United States); Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Oxford (United Kingdom)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE), Reactor Fleet and Advanced Reactor Development. Nuclear Reactor Technologies; USDOE Office of Nuclear Energy (NE), Fuel Cycle Technologies (NE-5); Engineering and Physical Sciences Research Council (EPSRC)

OSTI Identifier:: 1432160

Alternate Identifier(s):: OSTI ID: 1548544

Grant/Contract Number:: AC05-00OR22725; AC07-05ID14517; NE0000639; EP/L025817/1; EP/M022803/1; AC07-051D14517

Resource Type:: Journal Article: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 504; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS; 36 MATERIALS SCIENCE; microstructure; radiation-induced segregation; swelling; radiation-induced precipitates

Citation Formats


                    Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., and Was, G. S. Microstructure evolution of T91 irradiated in the BOR60 fast reactor.  United States: N. p., 2018. 
        Web.  doi:10.1016/j.jnucmat.2018.03.024.

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                    Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., & Was, G. S. Microstructure evolution of T91 irradiated in the BOR60 fast reactor.  United States.  https://doi.org/10.1016/j.jnucmat.2018.03.024

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                    Jiao, Z., Taller, S., Field, K., Yeli, G., Moody, M. P., and Was, G. S. 2018.  
        "Microstructure evolution of T91 irradiated in the BOR60 fast reactor".  United States.  https://doi.org/10.1016/j.jnucmat.2018.03.024.  https://www.osti.gov/servlets/purl/1432160.

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@article{osti_1432160,

  title        = {Microstructure evolution of T91 irradiated in the BOR60 fast reactor},

  author       = {Jiao, Z. and Taller, S. and Field, K. and Yeli, G. and Moody, M. P. and Was, G. S.},

  abstractNote = {In this paper, microstructures of T91 neutron irradiated in the BOR60 reactor at five temperatures between 376 °C and 524 °C to doses between 15.4 and 35.1 dpa were characterized using transmission electron microscopy (TEM), scanning transmission electron microscopy (STEM), and atom probe tomography (APT). Type a<100> dislocation loops were observed at 376–415 °C and network dislocations dominated at 460 °C and 524 °C. Cavities appeared in a bimodal distribution with a high density of small bubbles less than 2 nm at irradiation temperatures between 376 °C and 415 °C. Small bubbles were also observed at 460 °C and 524 °C but cavities greater than 2 nm were absent. Enrichment of Cr, Ni, and Si at the grain boundary was observed at all irradiation temperatures. Radiation-induced segregation (RIS) of Cr, Ni and Si appeared to saturate at 17.1 dpa and 376 °C. The temperature dependence of RIS of Cr, Ni and Si at the grain boundary, which showed a peak Cr enrichment temperature of 460 °C and a lower peak Ni and Si enrichment temperature of ~400 °C, was consistent with observations of RIS of Cr in proton irradiated T91, suggesting that the same RIS mechanism may also apply to BOR60 irradiated T91. G-phase and Cu-rich precipitates were observed at 376–415 °C but were absent at 460 °C and 524 °C. Finally, the absence of G-phase at 524 °C could be related to the minimal segregation of Ni and Si in that condition.},

  doi          = {10.1016/j.jnucmat.2018.03.024},

  url          = {https://www.osti.gov/biblio/1432160},
  journal      = {Journal of Nuclear Materials},

  issn         = {0022-3115},

  number       = ,

  volume       = 504,

  place        = {United States},

  year         = {Wed Mar 14 00:00:00 EDT 2018},

  month        = {Wed Mar 14 00:00:00 EDT 2018}

}

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Works referencing / citing this record:

Effect of Low-Temperature Ion Irradiation on the Nanostructure of 12% Chromium ChS-139 Steel
journal, September 2019

Rogozhkin, S. V.; Iskandarov, N. A.; Nikitin, A. A.
Inorganic Materials: Applied Research, Vol. 10, Issue 5
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Emulation of Radiation Damage of Structural Materials for Fission and Fusion Power Plants Using Heavy Ion Beams
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Rogozhkin, S. V.; Nikitin, A. A.; Khomich, A. A.
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Mn promotes the rate of nucleation and growth of precipitates by increasing Frenkel pairs in Fe–Cu based alloys
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Effect of low-temperature ion irradiation on the nanostructure of 12% chromium ChS-139 steel [Перестройка наноструктуры 12 %-й хромистой стали ЧС-139 при низкотемпературном облучении ионами]
journal, January 2019

Rogozhkin, S. V.; Iskandarov, N. A.; Nikitin, A. A.
Perspektivnye Materialy, Issue 5
https://doi.org/10.30791/1028-978x-2019-5-15-27

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Similar Records

Title: Microstructure evolution of T91 irradiated in the BOR60 fast reactor

Abstract

Citation Formats

Emulation of reactor irradiation damage using ion beams journal, October 2014

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure journal, January 2000

Microstructure of 9 Cr-1 MoVNb steel irradiated to 36 dpa at elevated temperatures in HFIR journal, May 1984

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

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

Microstructural analysis of neutron-irradiated martensitic steels journal, June 1996

SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184dpa at 413°C journal, September 2013

The microstructure and tensile properties of ferritic/martensitic steels T91, Eurofer-97 and F82H irradiated up to 20dpa in STIP-III journal, March 2010

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

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

Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys journal, April 2015

Diffraction contrast STEM of dislocations: Imaging and simulations journal, August 2011

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

The quantitative analysis of thin specimens journal, March 1975

The magnetic origin of anomalous high-temperature stability of dislocation loops in iron and iron-based alloys journal, April 2009

Dynamic observations of heavy-ion damage in Fe and Fe–Cr alloys journal, May 2009

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Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA journal, August 1995

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

Role of irradiated microstructure and microchemistry in irradiation-assisted stress corrosion cracking journal, February 2005

In situ study of heavy ion induced radiation damage in NF616 (P92) alloy journal, June 2012

Microstructural evolution in NF616 (P92) and Fe–9Cr–0.1C-model alloy under heavy ion irradiation journal, November 2015

Microstructural evolution of proton irradiated T91 journal, June 2006

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

Microstructure in martensitic steels T91 and F82H after irradiation in SINQ Target-3 journal, May 2003

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

Precipitate evolution in ion-irradiated HCM12A journal, June 2012

Cluster dynamics modeling of Mn-Ni-Si precipitates in ferritic-martensitic steel under irradiation journal, January 2018

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

Recent progress in understanding reactor pressure vessel steel embrittlement journal, June 1998

Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys journal, April 2011

Application of the inverse Kirkendall model of radiation-induced segregation to ferritic–martensitic alloys journal, June 2012

A systematic study of radiation-induced segregation in ferritic–martensitic alloys journal, November 2013

The mechanism of radiation-induced segregation in ferritic–martensitic alloys journal, February 2014

Effect of Low-Temperature Ion Irradiation on the Nanostructure of 12% Chromium ChS-139 Steel journal, September 2019

Emulation of Radiation Damage of Structural Materials for Fission and Fusion Power Plants Using Heavy Ion Beams journal, December 2019

Mn promotes the rate of nucleation and growth of precipitates by increasing Frenkel pairs in Fe–Cu based alloys journal, January 2019

Effect of low-temperature ion irradiation on the nanostructure of 12% chromium ChS-139 steel [Перестройка наноструктуры 12 %-й хромистой стали ЧС-139 при низкотемпературном облучении ионами] journal, January 2019

Emulation of reactor irradiation damage using ion beams
journal, October 2014

Comparison of swelling and irradiation creep behavior of fcc-austenitic and bcc-ferritic/martensitic alloys at high neutron exposure
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Microstructure of 9 Cr-1 MoVNb steel irradiated to 36 dpa at elevated temperatures in HFIR
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Microstructural development in reduced activation ferritic alloys irradiated to 200 dpa at 420°C
journal, September 1994

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

Microstructural analysis of neutron-irradiated martensitic steels
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SANS and TEM of ferritic–martensitic steel T91 irradiated in FFTF up to 184dpa at 413°C
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The microstructure and tensile properties of ferritic/martensitic steels T91, Eurofer-97 and F82H irradiated up to 20dpa in STIP-III
journal, March 2010

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

LAMDA: Irradiated-Materials Microscopy at Oak Ridge National Laboratory
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Application of STEM characterization for investigating radiation effects in BCC Fe-based alloys
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Diffraction contrast STEM of dislocations: Imaging and simulations
journal, August 2011

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

The quantitative analysis of thin specimens
journal, March 1975

The magnetic origin of anomalous high-temperature stability of dislocation loops in iron and iron-based alloys
journal, April 2009

Dynamic observations of heavy-ion damage in Fe and Fe–Cr alloys
journal, May 2009

Ion-irradiation-induced microstructural modifications in ferritic/martensitic steel T91
journal, July 2017

Swelling and dislocation evolution in simple ferritic alloys irradiated to high fluence in FFTF/MOTA
journal, August 1995

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

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In situ study of heavy ion induced radiation damage in NF616 (P92) alloy
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Microstructural evolution in NF616 (P92) and Fe–9Cr–0.1C-model alloy under heavy ion irradiation
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Microstructural evolution of proton irradiated T91
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The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels
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Microstructure in martensitic steels T91 and F82H after irradiation in SINQ Target-3
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Phase stability in proton and heavy ion irradiated ferritic–martensitic alloys
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Cluster dynamics modeling of Mn-Ni-Si precipitates in ferritic-martensitic steel under irradiation
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Phase stability of an HT-9 duct irradiated in FFTF
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journal, June 1998

Assessment of radiation-induced segregation mechanisms in austenitic and ferritic–martensitic alloys
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A systematic study of radiation-induced segregation in ferritic–martensitic alloys
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