b'Understanding of Degradation of SiC-SiC Materials in Nuclear Systems and Development of Mitigation StrategiesPrincipal Investigator: Peter HosemannTeam Members/ Collaborator: Joey Kabel, Ryan Schoell, Sebastian Lam, Djamel Kaoumi, Christian Deck, Kirill Shapovalov, Julie Tucker, Yongqiang Wang, Enguerrand Buckel, Aaron Mengel, Jia-Hong Ke Our results show that PVD based techniques can be used to identify suitable coatings and CVD processes can be introduced to the manufacturing process of SiC/SiC composites.Figure 1. Joey Kabel performing hardness measurementsS ilicon carbide has been a studieddiscussion as micro-crack evolution as an accident tolerant fuel (ATF)within the matrix material can lead cladding to combat ongoingto fission gas release and further challenges with zirconium-basedoxidation. The development of alloys. SiC fiber /PyC interphase /SiC matrix a barrier coating would mitigate composites were chosen initiallythese issues and hopefully bring SiC due to their favorable propertiescomposites to nuclear feasibility.regarding oxidation, neutron irradia-tion tolerance, high temperatureProject Description:strength, and neutronics, however,This research aims to develop a dual-two feasibility challenges still havepurpose barrier coating which can inhibited development of a nuclearbe commercially applied to SiCgrade SiC composite. Hydrothermalmatrix composites to enhance their corrosion on the surface of thecorrosion and mechanical proper-composite occurs at concerningties within nuclear environments. rates within boiling water reactorThe first technical objective of this (BWR) environments with the oxideproject was to identify coating layer dissolving at 10m/year.systems which would enhance Hermeticity also is another point ofSiC performance. This includes 52 2022|AFC ACCOMPLISHMENTS'