b'Neutron Irradiation on First-Generation Coated SiC/SiC CompositesTeam Members/ Collaborators: Takaaki Koyanagi, Stephen S. Raiman and Yutai Katoh (ORNL), Peter J. Doyle and Caen Ang (UTK), David M Carpenter and Kaicho Sun (MIT)Figure 1. Image showing SiCE xtensive development of silicon carbide (SiC) fiberreinforced SiC matrix composite cladding for light water reactors (LWRs) has fiberreinforced SiC matrixidentified benefits of the concept, composite tube coated with CrN. The tube length is 110 mm. including its inherent accident resistance and neutronic performance. Although SiC cladding appears to be attractive, critical feasibility issues such as hydrothermal corrosion and potential loss of fission gas retention due to cracking under normal operating conditions must be addressed. A possible solution to both issues is the application of a mitigating coating on the outer surface of the cladding. The team at Oak Ridge National Laboratory (ORNL) developed first-generation metal and ceramic thin coatings on a SiC composite tube (Figure 1). This research investigated responses of the coatings to neutron irradiation.Project Description:The objective of this research is to understand the effects of neutron irradiation on the coating microstructure and then to provide feedback toward optimization of coating microstructure and 86 2019|AFC ACCOMPLISHMENTS'