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A low-waste technology for the reprocessing of spent nuclear fuel (SNF) has been developed recently, which involves the conversion of actinide and lanthanide oxides with liquid N 2 O 4  into their nitrates followed by supercritical fluid extraction of the nitrates. The possibility of the reprocessing of SNF from high-temperature gas-cooled reactors (HTGRs) with nitrate conversion and supercritical fluid extraction is a current area of research in China. Here, a UO 2 -CeO 2  solid solution was prepared as a surrogate for a UO 2 -PuO 2  solid solution, and the recovery of U and Ce from the UO 2 -CeO 2  solid solution with liquid N 2 O 4  and supercritical CO 2  containing tri-n-butyl phosphate (TBP) was investigated. The UO 2 -CeO 2  solid solution prepared by electrolytic reduction-coprecipitation method had square plate microstructures. The solid solution after heat treatment was completely converted into nitrates with liquid N 2 O 4 . The XRD pattern of the nitrates was similar to that of UO 2 (NO 3 ) 2  ·3H 2 O. After 120 min of online extraction at 25 MPa and 50 ℃, 99.98% of the U and 98.74% of the Ce were recovered from the nitrates with supercritical CO 2  containing TBP. The results suggest a promising potential technology for the reprocessing of SNF from HTGRs.

Nitrate conversion and supercritical fluid extraction of UO 2 -CeO 2 solid solution prepared by an electrolytic reduction-coprecipitation method