Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C

He, Lingfeng; Harp, Jason M.; Hoggan, Rita E.; Wagner, Adrian R.

doi:10.1016/j.jnucmat.2017.01.035

Title: Microstructure studies of interdiffusion behavior of U₃Si₂/Zircaloy-4 at 800 and 1000 °C

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Abstract

Fuel swelling during normal reactor operations could lead to unfavorable chemical interactions when in contact with its cladding. As new fuel types are developed, it is crucial to understand the interaction behavior between fuel and its cladding. Diffusion experiments between U₃Si₂ and Zricaloy-4 (Zry-4) were conducted at 800 and 1000°C up to 100 hours. The microstructure of pristine U₃Si₂ and U₃Si₂/Zry-4 interdiffusion products were examined using scanning electron microscopy (SEM) and transmission electron microscopy (TEM) equipped with an energy dispersive X-ray spectroscopy (EDS) system. The primary interdiffusion product observed at 800°C is ZrSi₂, with secondary phases of U-Zr in the Zry-4, and Fe-Cr-W-Zr-Si phases at Zry-4/ZrSi₂ interface and Fe-Cr-U-Si phases at ZrSi₂/U-Si interface. As a result, the primary interdiffusion products at 1000°C were Zr₂Si, U-Zr-Fe-Ni, U, U-Zr, and a low melting point phase U₆Fe.

Authors:

^[1];

^[1]; Hoggan, Rita E. ^[1]; Wagner, Adrian R. ^[1]

Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: Sun Jan 22 00:00:00 EST 2017

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1357771

Alternate Identifier(s):: OSTI ID: 1419388

Report Number(s):: INL-JOU-16-40511
Journal ID: ISSN 0022-3115; PII: S0022311516311114

Grant/Contract Number:: AC07-05ID14517; FOA-0000712

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 486; Journal Issue: C; Journal ID: ISSN 0022-3115

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; accident tolerant fuel; diffusion; microstructure; nuclear fuels; zirconium alloy

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                    He, Lingfeng, Harp, Jason M., Hoggan, Rita E., and Wagner, Adrian R. Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C.  United States: N. p., 2017. 
Web.  doi:10.1016/j.jnucmat.2017.01.035.

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                    He, Lingfeng, Harp, Jason M., Hoggan, Rita E., & Wagner, Adrian R. Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C.  United States.  https://doi.org/10.1016/j.jnucmat.2017.01.035

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                    He, Lingfeng, Harp, Jason M., Hoggan, Rita E., and Wagner, Adrian R. Sun .  
"Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C".  United States.  https://doi.org/10.1016/j.jnucmat.2017.01.035.  https://www.osti.gov/servlets/purl/1357771.

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@article{osti_1357771,

  title        = {Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C},

  author       = {He, Lingfeng and Harp, Jason M. and Hoggan, Rita E. and Wagner, Adrian R.},

  abstractNote = {Fuel swelling during normal reactor operations could lead to unfavorable chemical interactions when in contact with its cladding. As new fuel types are developed, it is crucial to understand the interaction behavior between fuel and its cladding. Diffusion experiments between U3Si2 and Zricaloy-4 (Zry-4) were conducted at 800 and 1000°C up to 100 hours. The microstructure of pristine U3Si2 and U3Si2/Zry-4 interdiffusion products were examined using scanning electron microscopy (SEM) and transmission electron microscopy (TEM) equipped with an energy dispersive X-ray spectroscopy (EDS) system. The primary interdiffusion product observed at 800°C is ZrSi2, with secondary phases of U-Zr in the Zry-4, and Fe-Cr-W-Zr-Si phases at Zry-4/ZrSi2 interface and Fe-Cr-U-Si phases at ZrSi2/U-Si interface. As a result, the primary interdiffusion products at 1000°C were Zr2Si, U-Zr-Fe-Ni, U, U-Zr, and a low melting point phase U6Fe.},

  doi          = {10.1016/j.jnucmat.2017.01.035},

  journal      = {Journal of Nuclear Materials},

  number       = C,

  volume       = 486,

  place        = {United States},

  year         = {Sun Jan 22 00:00:00 EST 2017},

  month        = {Sun Jan 22 00:00:00 EST 2017}

}

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Title: Microstructure studies of interdiffusion behavior of U3Si2/Zircaloy-4 at 800 and 1000 °C

Abstract

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Title: Microstructure studies of interdiffusion behavior of U₃Si₂/Zircaloy-4 at 800 and 1000 °C