Straight chain N,N-dihexyloctanamide (DHOA) has been identified as a promising alternative of tributyl phosphate (TBP) in the reprocessing of irradiated uranium based fuels. This article deals with the evaluation of DHOA vis-a-vis TBP as extractant in counter-current runs employing centrifugal contactors for uranium extraction from feed solutions of varying compositions such as uranium solutions (20, 50.4g/L) at acidities (1-4M HNO3), and simulated Advanced Heavy Water Reactor (AHWR) spent fuel dissolver solution. Experiments were also carried out to recover uranium from assorted organic waste solutions. Dispersion number of DHOA was calculated prior to counter-current runs and compared with different solvents proposed for back-end of fuel cycle. These runs demonstrated that DHOA is a promising alternative of TBP for various hydrometallurgical operations dealing with the recovery of uranium from solutions of various origins including spent fuel dissolver solutions.