Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding

Gigax, Jonathan G.; Kennas, Miltiadis; Kim, Hyosim; Wang, Tianyao; Maier, Benjamin R.; Yeom, Hwasung; Johnson, Greg O.; Sridharan, Kumar; Shao, Lin

doi:10.1016/j.jnucmat.2019.05.021

Title: Radiation response of Ti₂AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding

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Abstract

A Ti₂AlC MAX phase material was deposited on Zircaloy-4 substrate using the cold spray process, with the goal of enhancing the accident tolerance of zirconium-alloy fuel cladding in light water reactors. The samples were annealed up to 923 K to study the intermetallic phase formation between the coating and Zircaloy-4 substrate. Three interface compounds, ZrAl₂, ZrAl, and Zr₃Al, were identified and the activation energy of the interfacial intermetallic compound growth was determined. The radiation response of the coating material and interfacial intermetallic compounds after 3.5 MeV Zr²⁺ ion irradiation was investigated by transmission electron microscopy and nanoindentation. Ion irradiation disrupted the nanolamellar structure of the Ti₂AlC coating while amorphization was observed some of the intermetallic compounds. Furthermore, nanoindentation revealed overall hardening of the Ti₂AlC coating and Zr₃Al phase, with no significant change observed in the ZrAl₂ and ZrAl phases.

Authors:

^[1]; Kennas, Miltiadis ^[2]; Kim, Hyosim ^[2];

^[2];

^[3]; Yeom, Hwasung ^[3]; Johnson, Greg O. ^[3]; Sridharan, Kumar ^[3]; Shao, Lin ^[2]

Texas A & M Univ., College Station, TX (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Texas A & M Univ., College Station, TX (United States)
Univ. of Wisconsin-Madison, Madison, WI (United States)

Publication Date:: Sat May 11 00:00:00 EDT 2019

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

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

OSTI Identifier:: 1514978

Alternate Identifier(s):: OSTI ID: 1776017

Report Number(s):: LA-UR-18-23398
Journal ID: ISSN 0022-3115

Grant/Contract Number:: 89233218CNA000001

Resource Type:: Accepted Manuscript

Journal Name:: Journal of Nuclear Materials

Additional Journal Information:: Journal Volume: 523; 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 cladding; Ion irradiation; Intermetallic formation; Nanomechanical testing

Citation Formats


                    Gigax, Jonathan G., Kennas, Miltiadis, Kim, Hyosim, Wang, Tianyao, Maier, Benjamin R., Yeom, Hwasung, Johnson, Greg O., Sridharan, Kumar, and Shao, Lin. Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding.  United States: N. p., 2019. 
Web.  doi:10.1016/j.jnucmat.2019.05.021.

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                    Gigax, Jonathan G., Kennas, Miltiadis, Kim, Hyosim, Wang, Tianyao, Maier, Benjamin R., Yeom, Hwasung, Johnson, Greg O., Sridharan, Kumar, & Shao, Lin. Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding.  United States.  https://doi.org/10.1016/j.jnucmat.2019.05.021

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                    Gigax, Jonathan G., Kennas, Miltiadis, Kim, Hyosim, Wang, Tianyao, Maier, Benjamin R., Yeom, Hwasung, Johnson, Greg O., Sridharan, Kumar, and Shao, Lin. Sat .  
"Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding".  United States.  https://doi.org/10.1016/j.jnucmat.2019.05.021.  https://www.osti.gov/servlets/purl/1514978.

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@article{osti_1514978,

  title        = {Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding},

  author       = {Gigax, Jonathan G. and Kennas, Miltiadis and Kim, Hyosim and Wang, Tianyao and Maier, Benjamin R. and Yeom, Hwasung and Johnson, Greg O. and Sridharan, Kumar and Shao, Lin},

  abstractNote = {A Ti2AlC MAX phase material was deposited on Zircaloy-4 substrate using the cold spray process, with the goal of enhancing the accident tolerance of zirconium-alloy fuel cladding in light water reactors. The samples were annealed up to 923 K to study the intermetallic phase formation between the coating and Zircaloy-4 substrate. Three interface compounds, ZrAl2, ZrAl, and Zr3Al, were identified and the activation energy of the interfacial intermetallic compound growth was determined. The radiation response of the coating material and interfacial intermetallic compounds after 3.5 MeV Zr2+ ion irradiation was investigated by transmission electron microscopy and nanoindentation. Ion irradiation disrupted the nanolamellar structure of the Ti2AlC coating while amorphization was observed some of the intermetallic compounds. Furthermore, nanoindentation revealed overall hardening of the Ti2AlC coating and Zr3Al phase, with no significant change observed in the ZrAl2 and ZrAl phases.},

  doi          = {10.1016/j.jnucmat.2019.05.021},

  journal      = {Journal of Nuclear Materials},

  number       = ,

  volume       = 523,

  place        = {United States},

  year         = {Sat May 11 00:00:00 EDT 2019},

  month        = {Sat May 11 00:00:00 EDT 2019}

}

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Title: Radiation response of Ti2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding

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Title: Radiation response of Ti₂AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding