Exposure to high temperatures and irradiation results in interaction and interdiffusion between fuel and cladding constituents that can lead to formation of undesirable brittle or low-melting point phases. A diffusion couple study has been conducted to understand fuel-cladding interaction occurring between U-22Pu-4Zr (in wt%) fuel and pure Fe at elevated temperatures. The phases formed within fuel cladding chemical interaction (FCCI) layer have been characterized in the transmission electron microscope (TEM). The phases formed within FCCI layer have been identified as Fe 2 U (Fd-3m), FeU 6 (I4/mcm), Fe 2 Zr (Fd-3m), FeZr 2 (I4/mcm), Fe 2 Pu (Fd-3m), UZr 2 (P6/mmm), β-Zr (Im-3m), and ZrO 2 (Fm-3m).