Characterization of Long-Term, In-Reactor Zircaloy-4 Corrosion Coupons and the Impact of Flux, Fluence, and Temperature on Oxide Growth, Stress Development, Phase Formation, and Grain Size

Abstract

Eleven Zircaloy-4 samples were irradiated in the Advanced Test Reactor at a variety of temperatures and neutron flux levels for up to 6.5 years. Subsequently, the coupons were characterized with complementary techniques to understand the mechanisms behind oxide growth as a function of different corrosion environments. Samples were examined using synchrotron X-ray diffraction/ fluorescence, traditional X-ray diffraction, focused ion beam/scanning electron microscopy serial sectioning, and three-dimensional reconstruction to develop Manuscript received March 28, 2019; accepted for publication August 13, 2019. Dept. of Mechanical and Nuclear Engineering, The Pennsylvania State University, University Park, PA 16802, USA B. E. http://orcid.org/0000-0002-4592-7147, A. T. M. http://orcid.org/0000-0001-5735-1491 Naval Nuclear Laboratory, Schenectady, NY 12301, USA Naval Nuclear Laboratory, West Mifflin, PA 15122, USA Advanced Photon Source, Argonne National Laboratory, Argonne, IL 60439, USA ASTM 19th International Symposium on Zirconium in the Nuclear Industry on May 19–23, 2019 in