Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime

Katoh, Yutai; Koyanagi, Takaaki; McDuffee, Joel L.; Snead, Lance L.; Yueh, Ken

doi:10.1016/j.jnucmat.2017.12.009

Title: Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime

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Abstract

Swelling, or volumetric expansion, is an inevitable consequence of the atomic displacement damage in crystalline silicon carbide (SiC) caused by energetic neutron irradiation. Because of its steep temperature and dose dependence, understanding swelling is essential for designing SiC-based components for nuclear applications. Here in this study, swelling behaviors of monolithic CVD SiC and nuclear grade SiC fiber – SiC matrix (SiC/SiC) composites were accurately determined, supported by the irradiation temperature determination for individual samples, following neutron irradiation within the lower transition swelling temperature regime. Slightly anisotropic swelling behaviors were found for the SiC/SiC samples and attributed primarily to the combined effects of the pre-existing microcracking, fiber architecture, and specimen dimension. A semi-empirical model of SiC swelling was calibrated and presented. Finally, implications of the refined model to selected swelling-related issues for SiC-based nuclar reactor components are discussed.

Authors:

^[1];

^[2];

^[2]; Snead, Lance L. ^[3]; Yueh, Ken ^[4]

Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Univ. of Tennessee, Knoxville, TN (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Massachusetts Inst. of Technology (MIT), Cambridge, MA (United States)
Electric Power Research Inst., Charlotte, NC (United States)

Publication Date:: 2017-12-08

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

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE), Reactor Fleet and Advanced Reactor Development. Nuclear Reactor Technologies; USDOE Office of Science (SC), Fusion Energy Sciences (FES)

OSTI Identifier:: 1414701

Alternate Identifier(s):: OSTI ID: 1548913

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 499; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 22 GENERAL STUDIES OF NUCLEAR REACTORS

Citation Formats


                    Katoh, Yutai, Koyanagi, Takaaki, McDuffee, Joel L., Snead, Lance L., and Yueh, Ken. Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime.  United States: N. p., 2017. 
Web.  doi:10.1016/j.jnucmat.2017.12.009.

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                    Katoh, Yutai, Koyanagi, Takaaki, McDuffee, Joel L., Snead, Lance L., & Yueh, Ken. Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime.  United States.  https://doi.org/10.1016/j.jnucmat.2017.12.009

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                    Katoh, Yutai, Koyanagi, Takaaki, McDuffee, Joel L., Snead, Lance L., and Yueh, Ken. Fri .  
"Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime".  United States.  https://doi.org/10.1016/j.jnucmat.2017.12.009.  https://www.osti.gov/servlets/purl/1414701.

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@article{osti_1414701,

  title        = {Dimensional stability and anisotropy of SiC and SiC-based composites in transition swelling regime},

  author       = {Katoh, Yutai and Koyanagi, Takaaki and McDuffee, Joel L. and Snead, Lance L. and Yueh, Ken},

  abstractNote = {Swelling, or volumetric expansion, is an inevitable consequence of the atomic displacement damage in crystalline silicon carbide (SiC) caused by energetic neutron irradiation. Because of its steep temperature and dose dependence, understanding swelling is essential for designing SiC-based components for nuclear applications. Here in this study, swelling behaviors of monolithic CVD SiC and nuclear grade SiC fiber – SiC matrix (SiC/SiC) composites were accurately determined, supported by the irradiation temperature determination for individual samples, following neutron irradiation within the lower transition swelling temperature regime. Slightly anisotropic swelling behaviors were found for the SiC/SiC samples and attributed primarily to the combined effects of the pre-existing microcracking, fiber architecture, and specimen dimension. A semi-empirical model of SiC swelling was calibrated and presented. Finally, implications of the refined model to selected swelling-related issues for SiC-based nuclar reactor components are discussed.},

  doi          = {10.1016/j.jnucmat.2017.12.009},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 499,

  place        = {United States},

  year         = {2017},

  month        = {12}

}

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