Patent Number: 
Section: claims

1. A method for treating carbonaceous radioactive waste, comprising the delivery of waste to one or more radioactive isotope separation stations, said isotopes being among at least carbon 14, chlorine 36, and tritium,wherein the delivery to each of the stations occurs in wet form,the method comprising:providing a leaching to separate the chlorine 36 and the tritium from the rest of the carbonaceous waste so as to deliver the chlorine 36 and the tritium in at least one first separation station, andafter separations of the chlorine 36 and the tritium from the rest of the carbonaceous waste, treating the rest of the carbonaceous waste so as to deliver the carbon 14 in a second separation station. 2. The method according to claim 1, wherein specific separation stations are provided for each element among the carbon 14, chlorine 36, and tritium, as well as delivery in wet form to each of said stations. 3. The method according to claim 1, wherein the waste is crushed and mixed with water for delivery in slurry form, before a first isotopic separation. 4. The method according to claim 1, wherein the waste is mixed with water to form a slurry, then mechanically filtered and dried, and wherein the water issuing from this drying contains all or part of the chlorine 36 initially present in the waste prior to drying. 5. The method according to claim 1, wherein, after separating the chlorine 36, the waste is calcined by roasting, then washed, and wherein the water recovered from the wash contains all or part of the tritium initially present in the waste prior to roasting. 6. The method according to claim 1, wherein, with at least a portion of the waste being calcined by roasting, the waste resulting from the roasting is oxidized to carbon dioxide form for dissolution in the conveying water. 7. The method according to claim 1, wherein the carbon 14 is put in carbon dioxide form for treatment by carbonation reaction, in order to be solidified and stored in solid form. 8. The method according to claim 1, wherein the carbonaceous waste initially contains graphite. 9. A facility for treating carbonaceous radioactive waste, comprising one or more radioactive isotope separation stations, said isotopes being among at least carbon 14, chlorine 36, and tritium, as well as means of delivering the waste to said stations,wherein the means of delivery are supplied with water in order to deliver the waste in wet form,said facility including a leaching stage to separate the chlorine 36 and the tritium from the rest of the carbonaceous waste and to deliver the chlorine 36 and the tritium in at least one first separation station of the facility, anda reactor for treating the rest of the carbonaceous waste so as to deliver the carbon 14 in a second separation station of the facility.