[en] Curium is closely associated with americium in irradiated fuels because of their chemical similarity with regard to potential separation requirements, and because americium also requires special shielding and handling requirements due to its gamma radiation emission. Americium is produced in greater mass than curium in irradiated nuclear fuels and the mass ratio can grow exponentially with decay time because of the simultaneous decay of "2"4"4Cm and in-growth of "2"4"1Am from decay of "2"4"1Pu (half-life = 14.4 years). For these reasons, curium management is challenging. Countries that are now engaged in or planning future fuel recycle operations, are considering methods to manage the curium produced and minimise the shielding and handling requirements, as well as the reprocessing requirements for separation of curium from americium France, Japan, and the USA have begun curium management studies. Curium management methods under consideration include (1) separation of curium from americium and storage of curium for several decades to allow "2"4"4Cm to decay substantially to "2"4"0Pu, while moving ahead to recycle americium; (2) recycling of americium and curium without separation; and (3) waiting several decades to reprocess used nuclear fuels, allowing decay minimisation of curium emissions and the requirement for separation of curium from americium, and allowing an alteration of the subsequent transmutation path to reduce the production of curium in recycled used fuels. In this report, recent curium management studies in France, Japan, and the USA have been described. The French studies included scenarios that compared the recycle of ail minor actinides (neptunium, americium, and curium) with the recycle of only neptunium and americium in radial blankets of sodium-cooled fast reactors (SFR). In the latter scenario, curium is separated from americium during used fuel reprocessing and stored for 5000 years to allow "2"4"4Cm to decay to "2"4"0Pu which is then recycled. Even though the studies showed that the recycle of all MAs provides the most efficient decreases of radio-toxic inventory and decay heat in the high level waste, the removal and decay storage of curium allows overall reductions while minimising the neutron shielding and handling requirements during fuel recycle irradiations. Thus, French separations studies have been directed toward americium separation from curium and fission products in a single process. The development of the ExAm process can accomplish the needed recovery of americium. The Japanese studies compare Minor Actinide (MA) isotope production in (1) low-enriched uranium LWR used fuel, (2) in U-Pu mixed oxide (MOX) used fuel, (3) in Fast Breeder Reactor (FBR) MOX used fuel, and (4) in FBR U-Transuranium (TRU) MOX used fuel. The studies show the effects of increasing decay time following irradiation on decay heat generation from both fission products and actinide isotopes. The decay time effects of decreasing "2"4"4Cm and fission product inventory with a simultaneous increase in the "2"4"1Am inventory are shown. Also, the Japanese studies describe curium separation process development by means of extraction chromatography methods. The USA studies describe the radioactive decay effects and indications on mass, heat, and radio toxicity amounts and ratios of curium and americium. Also shown is the decreased curium production during transmutation of actinides after several decades of decay storage, prior to used fuel reprocessing. Curium inventory is compared for recycle scenarios using LWRs or fast reactors with either 10-year or 35-year fuel cycles. (authors)