In the Fukushima Daiichi Nuclear Power Plant accident, nuclear fission reaction was stopped successfully after the earthquake. However, due to the failure of cooling by the station blackout, the cladding temperature rose and the cladding reacted with high-temperature steam, causing a hydrogen explosion, scattering radioactive materials over a wide area and injuring many residents. After this accident, many countries around the world started to develop cladding materials that do not generate hydrogen or generate little hydrogen even at high temperatures. Silicon carbide is one of the new cladding material candidates. It hardly reacts with high-temperature steam, and its melting point is much higher (2730℃) than the melting point (1852℃) of Zircaloy, the current cladding material. Moreover, the thermal neutron absorption cross-section is smaller than that of the Zircaloy alloy, and it is superior in terms of nuclear performance. On the other hand, since silicon carbide is a ceramic, when the diameter of the uranium dioxide pellet increases due to swelling at high burnup, the effect of pellet-cladding interaction (PCI) is a concern. In this study, the fuel behavior analysis code FEMAXI-8 was used to quantify the interaction between the uranium dioxide pellets and the SiC cladding at high burnup. It was confirmed that the cladding stress increased sharply when it exceeded over 70GWd/tU. Although the cladding stress is below the yield strength, it was understood that it is necessary to change the dimensions, shape, and material of fuel so that PCI does not become excessive in fuel design.