The potential of a catalyzed fusion-driven fast hybrid blanket to regenerate Canada deuterium uranium (CANDU) spent fuel is investigated. The investigations are done to achieve enrichment grades of fissile isotopes (EGFIs) in four applications: 1. recycling in a conventional commercial CANDU reactor (EGFI = 0.71 to 0.9%) 2. recycling in an advanced conceptual CANDU reactor with a high burnup rate (EGFI = 1%) 3. recycling in an advanced breeder with thorium fuel (EGFI > 1.5%) 4. recycling in a conventional light water reactor (LWR)(EGFI>3%). The regeneration periods of 5 to 7, 6 to 9, 12 to 15, and >30 months, respectively, are evaluated for the four reactor types under a first-wall fusion neutron current load of 1014(2.45-MeV n)/cm2-s and 1014(14.1-MeV n)/cm2-s, corresponding to 2.64 MW/m2 and a plant factor of 75%. During the regeneration process, the burnup rates vary from 2000 MWd/t (for conventional CANDU) to 10000 MWd/t (forLWRs), so that multiple recycling becomes possible.