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A typical high active waste (HAW) arising from reprocessing of the nuclear fuel –(U 0.3 Pu 0.7 )C irradiated to the burn-up of 155 GWd/Te in a Fast Breeder Test Reactor (FBTR) was characterized by various analytical techniques. The target element was separated from other interferences or pre-concentrated by a suitable technique such as solvent extraction, chromatographic methods  etc.  The results obtained from various techniques are compared. The implications of the estimated composition in handling, treatment and disposal of HAW are discussed.

Characterization of high active waste (155 GWd/Te) arising from fast reactor fuel reprocessing