b'Advanced Fast Reactor Cladding DevelopmentPrincipal Investigator: David T. Hoelzer (ORNL)Team Members/ Collaborators: Caleb P. Massey and Rachel L. Seibert (ORNL)Figure 1. Microstructural features of Oak Ridge Fast Reactor Advanced Fuel Cladding (OFRAC) a) Back-scattered Electron (BSE) Scanning Electron Microscopy (SEM) micrograph of the ultra-fine grains, b) Scanning Transmission Electron Microscopy (STEM) Energy Dispersive X-Ray Spectroscopy (EDS) map of Nb and Ti overlaid to show the Nb(C,N) particles and c) LEAP element map of the Ti-Y-O nano-size oxide particles. T he Nuclear Technology Research(e.g., >40%) in a fast neutron flux. The and Development (NTRD)cladding must withstand mechanical program is investigatingproperty degradation due to swelling advanced nuclear fuel cladding thatand creep deformation upon exposure will enable the development of newto very high neutron doses of >200 fuel for irradiating to very high burnupdisplacements per atom (dpa) at 186 2019|AFC ACCOMPLISHMENTS'