Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations

doi:10.1016/j.jnucmat.2018.03.002

Title: Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations

Abstract

FeCrAl ferritic alloys are excellent cladding candidates for accident tolerant fuel systems due to their high resistance to oxidation as a result of formation of a protective Al₂O₃ scale at high temperatures in steam. In this study, we report the irradiation response of the 10Cr and 13Cr FeCrAl cladding tubes under Fe²⁺ ion irradiation up to ~16 dpa at 300 °C. Dislocation loop size, density and characteristics were determined using both two beam bright field transmission electron microscopy and on-zone scanning transmission electron microscopy techniques. 10Cr (C06M2) tube has a lower dislocation density, larger grain size and a slightly weaker texture compared to the 13Cr (C36M3) tube before irradiation. After irradiation to 0.7 dpa and 16 dpa, the fraction of <100> type sessile dislocations decreases with increasing Cr amount in the alloys. It has been found that there is neither void formation nor α' precipitation as a result of ion irradiations in either alloy. Therefore, dislocation loops were determined to be the only irradiation induced defects contributing to the hardening. Nanoindentation testing before the irradiation revealed that the average nanohardness of the C36M3 tube is higher than that of the C06M2 tube. The average nanohardness of irradiated tube samples saturatedmore »« less

Authors:

^[1]; Weaver, J. S. ^[1]; Maloy, S. A. ^[1]; El-Atwani, O. ^[1]; Wang, Y. Q. ^[1]; Mara, N. A. ^[1]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Publication Date:: 2018-03-02

Research Org.:: Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE); USDOE National Nuclear Security Administration (NNSA)

OSTI Identifier:: 1425772

Alternate Identifier(s):: OSTI ID: 1548647

Report Number(s):: LA-UR-18-20922
Journal ID: ISSN 0022-3115; TRN: US1802164

Grant/Contract Number:: AC52-06NA25396

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 503; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 36 MATERIALS SCIENCE

Citation Formats


                    Aydogan, E., Weaver, J. S., Maloy, S. A., El-Atwani, O., Wang, Y. Q., and Mara, N. A. Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations.  United States: N. p., 2018. 
        Web.  doi:10.1016/j.jnucmat.2018.03.002.

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                    Aydogan, E., Weaver, J. S., Maloy, S. A., El-Atwani, O., Wang, Y. Q., & Mara, N. A. Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations.  United States.  doi:10.1016/j.jnucmat.2018.03.002.

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                    Aydogan, E., Weaver, J. S., Maloy, S. A., El-Atwani, O., Wang, Y. Q., and Mara, N. A. Fri .  
        "Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations".  United States.  doi:10.1016/j.jnucmat.2018.03.002.  https://www.osti.gov/servlets/purl/1425772.

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@article{osti_1425772,

  title        = {Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations},

  author       = {Aydogan, E. and Weaver, J. S. and Maloy, S. A. and El-Atwani, O. and Wang, Y. Q. and Mara, N. A.},

  abstractNote = {FeCrAl ferritic alloys are excellent cladding candidates for accident tolerant fuel systems due to their high resistance to oxidation as a result of formation of a protective Al2O3 scale at high temperatures in steam. In this study, we report the irradiation response of the 10Cr and 13Cr FeCrAl cladding tubes under Fe2+ ion irradiation up to ~16 dpa at 300 °C. Dislocation loop size, density and characteristics were determined using both two beam bright field transmission electron microscopy and on-zone scanning transmission electron microscopy techniques. 10Cr (C06M2) tube has a lower dislocation density, larger grain size and a slightly weaker texture compared to the 13Cr (C36M3) tube before irradiation. After irradiation to 0.7 dpa and 16 dpa, the fraction of <100> type sessile dislocations decreases with increasing Cr amount in the alloys. It has been found that there is neither void formation nor α' precipitation as a result of ion irradiations in either alloy. Therefore, dislocation loops were determined to be the only irradiation induced defects contributing to the hardening. Nanoindentation testing before the irradiation revealed that the average nanohardness of the C36M3 tube is higher than that of the C06M2 tube. The average nanohardness of irradiated tube samples saturated at 1.6-2.0 GPa hardening for both tubes between ~3.4 dpa and ~16 dpa. The hardening calculated based on transmission electron microscopy was found to be consistent with nanohardness measurements.},

  doi          = {10.1016/j.jnucmat.2018.03.002},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 503,

  place        = {United States},

  year         = {2018},

  month        = {3}

}

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DOI: 10.1016/j.jnucmat.2018.03.002

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Figures / Tables:

Fig. 1: SRIM calculated damage and implanted atom profiles for 45 peak dpa with 5 MeV Fe²⁺ ions using Kinchin-Pease option at 40 eV displacement energy.

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Works referencing / citing this record:

α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys
journal, June 2019

Aydogan, E.; Martinez, E.; March, K.
Scientific Reports, Vol. 9, Issue 1
DOI: 10.1038/s41598-019-44508-5

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Title: Microstructure and mechanical properties of FeCrAl alloys under heavy ion irradiations

Abstract

Citation Formats

Figures / Tables:

α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys journal, June 2019

α′ formation kinetics and radiation induced segregation in neutron irradiated 14YWT nanostructured ferritic alloys
journal, June 2019