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Title: Radiation response of Ti 2AlC MAX phase coated Zircaloy-4 for accident tolerant fuel cladding

Abstract

A Ti 2AlC 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, ZrAl 2, ZrAl, and Zr 3Al, 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 Zr 2+ ion irradiation was investigated by transmission electron microscopy and nanoindentation. Ion irradiation disrupted the nanolamellar structure of the Ti 2AlC coating while amorphization was observed some of the intermetallic compounds. Furthermore, nanoindentation revealed overall hardening of the Ti 2AlC coating and Zr 3Al phase, with no significant change observed in the ZrAl 2 and ZrAl phases.

Authors:
ORCiD logo [1];  [2];  [2]; ORCiD logo [2]; ORCiD logo [3];  [3];  [3];  [3];  [2]
  1. Texas A & M Univ., College Station, TX (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
  2. Texas A & M Univ., College Station, TX (United States)
  3. Univ. of Wisconsin-Madison, Madison, WI (United States)
Publication Date:
Research Org.:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1514978
Report Number(s):
LA-UR-18-23398
Journal ID: ISSN 0022-3115
Grant/Contract Number:  
89233218CNA000001
Resource Type:
Journal Article: Accepted Manuscript
Journal Name:
Journal of Nuclear Materials
Additional Journal Information:
Journal Name: Journal of Nuclear Materials; Journal ID: ISSN 0022-3115
Publisher:
Elsevier
Country of Publication:
United States
Language:
English
Subject:
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.
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. doi:10.1016/j.jnucmat.2019.05.021.
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. doi:10.1016/j.jnucmat.2019.05.021.
@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},
issn = {0022-3115},
number = ,
volume = ,
place = {United States},
year = {2019},
month = {5}
}

Journal Article:
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