Radiation response of FeCrAl-coated Zircaloy-4

Kennas, Miltiadis; Kim, Hyosim; Gigax, Jonathan Gregory; Wang, Tianyao; Maier, Benjamin R; Yeom, Hwasung; Johnson, Greg O; Sridharan, Kumar; Peddicord, Kenneth L; Shao, Lin; Dabney, Tyler

doi:10.1016/j.jnucmat.2020.152175

Radiation response of FeCrAl-coated Zircaloy-4

Journal Article · Sat Aug 01 00:00:00 EDT 2020 · Journal of Nuclear Materials

DOI:https://doi.org/10.1016/j.jnucmat.2020.152175· OSTI ID:1616414

Kennas, Miltiadis ^[1]; ^[2]; ^[2]; Wang, Tianyao ^[1]; Maier, Benjamin R ^[3]; Yeom, Hwasung ^[3]; Johnson, Greg O ^[3]; Sridharan, Kumar ^[3]; Peddicord, Kenneth L ^[1]; Shao, Lin ^[1]; Dabney, Tyler ^[3]

Texas A & M Univ. at Galveston, TX (United States)
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Univ. of Wisconsin, Madison, WI (United States)

Coating the surface of Zircaloy-4 light water reactor fuel cladding tube is of considerable interest for enhancing its accident tolerance. In this study, thermal annealing of FeCrAl-coated Zircaloy-4 at 725 °C for 500 h, was used to induce interfacial reactions between Zircaloy-4 and FeCrAl. The interface zones were then irradiated by 3.5 MeV Zr ions at 400 °C, up to 50, 100, 150 peak dpa values. Transmission electron microscopy (TEM) and scanning TEM were used to characterize microstructural and composition changes before and after ion irradiation. Three interfacial phases were identified: FeZr₃, (Fe,Cr)₂Zr, and ZrC. The widest intermetallic layer, FeZr3, had large grains. The narrower phases, (Fe,Cr)2Zr and ZrC, contained small grains and were often mixed. The unexpected observation of the ZrC phase was attributed to the presence of very small impurity level concentrations of carbon in the powder material. No void swelling was observed in any of the phases, including the FeCrAl coating and Zircaloy-4 substrate. (Fe,Cr)₂Zr, however, fully amorphized after irradiation, even at the lowest dpa.

View Accepted Manuscript (DOE)

Research Organization:: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Organization:: USDOE

Grant/Contract Number:: 89233218CNA000001

OSTI ID:: 1616414

Alternate ID(s):: OSTI ID: 1619853

Report Number(s):: LA-UR--19-31527

Journal Information:: Journal of Nuclear Materials, Journal Name: Journal of Nuclear Materials Journal Issue: C Vol. 536; ISSN 0022-3115

Publisher:: ElsevierCopyright Statement

Country of Publication:: United States

Language:: English

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36 MATERIALS SCIENCE
Accident tolerant fuel cladding
Amorphous
FeCrAl
Intermetallic phase
Radiation
Zircaloy-4

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