Radiation response of FeCrAl-coated Zircaloy-4

• Published in: Journal of nuclear materials Vol. 536; no. C
• Main Authors: Kennas, Miltiadis, Kim, Hyosim, Gigax, Jonathan G., Wang, Tianyao, Maier, Benjamin R., Yeom, Hwasung, Johnson, Greg O., Dabney, Tyler, Sridharan, Kumar, Peddicord, Kenneth L., Shao, Lin
• Format: Journal Article
• Language: English
• Published: Netherlands Elsevier 01.08.2020
• Subjects: Accident tolerant fuel cladding; Amorphous; FeCrAl; Intermetallic phase; MATERIALS SCIENCE; Radiation; Zircaloy-4
• ISSN: 0022-3115; 1873-4820

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.