b'Characterization and Testing of Cr-Coated ZircaloyPrincipal Investigator: Stuart MaloyTeam Members/ Collaborators: Hyosim Kim, Nan Li, Cheng Liu, J. Kevin Baldwin, Kumar Sridharan (U. Wisconsin), Tyler Dabney (U. Wisconsin), Andy Nelson (ORNL), and Tim Graening (ORNL)Figure 1. Scanning Electron Microscopy (SEM) images of (a) cold spray coating without annealing, (b) cold spray coating after annealing at 1000 C for 1 hr, (c) HiPIMS coating, and (d) Physical Vapor Deposition (PVD) coatingB ecause of the events related toSome engineering alloys are presently the Fukushima reactor inci- available with promising properties, dent, innovative new claddingbut these alloys were not specifically materials are being investigated fordeveloped for LWR applications. Thus, light water reactors (LWRs) withwe are continuing development of improved resistance to accidentCr-coated zircaloy cladding material conditions such as a Loss of Coolantin collaboration with Oak Ridge Accident (LOCA). Materials needNational Laboratory (ORNL) and to be developed and tested to meetperforming mechanical testing and these challenging conditions. ion irradiation testing on this alloy58 2021|AFC ACCOMPLISHMENTS'