[en] The present waste management for already vitrified HLW has to be considered as an irreversible process for which disposal in geologic strata is the most advisable and unavoidable solution. Spent fuel discharged from nuclear power plants should be stored in engineered facilities as long as there is no definite choice of long term management of long-lived actinides. Retrievable storage in underground facilities is an alternative which could have its merits as a medium term policy. Conventional reprocessing of spent fuel is a necessary step in the reduction of the actinide content of HLW. The recycling of Pu and U into the MOX-fuel cycle is a transient solution to reduce the volume of actinide loaded waste. Spent LWR-MOX fuel with its high actinide content should be stored in engineered facilities till a safe fast reactor technology becomes available. Advanced reprocessing of (high-burn up) spent fuel with removal of U, and TRUs and production of actinide-free-vitrified-HLW is in the medium term the most defendable waste management option. Final disposal of actinide-free HLW in geologic strata is fully acceptable if the actinide content has been reduced with two (or more) orders of magnitude. Transformation of separated minor actinide concentrates into a ceramic type of waste form is beneficial from radiological point of view even if the deep disposal is the last resort. The sharply reduced solubility (compared to glass) reduces the long term environmental risk. Transformation into a matrix which could also be used as a future nuclear fuel- or target form is the most versatile option. Transmutation in a fast neutron reactor facility is the only possibility to incinerate the overall actinide (Pu+MA) inventory and to make use of the large amounts of plutonium present in spent LWR-MOX fuel. However the current FR technology with sodium cooling can, for safety reasons, not be considered for that purpose. The use of less dangerous metallic coolants is to be investigated. Multiple recycling of plutonium in critical FRs is the most economic way to reduce the accumulated plutonium inventory of LWR-MOX. This option asks for the development of new reprocessing technologies. Pyrochemical reprocessing techniques appear as almost indispensable to carry out multiple recycling of high burn up FR fuel within short cooling times. Critical fast reactors with an adapted coolant system could also be used as storage reactors for Minor Actinides and reduce significantly their inventory during a long irradiation period in a thermalized blanket. Separated Minor Actinides can theoretically be incinerated in accelerator driven transmutation systems (ADS). But a long range R and D effort will be necessary to develop the system from its present conceptual design stage to an industrial reality. The connection between the proton accelerator operating under vacuum and the subcritical reactor core operating under cover-gas pressure requires the development of a replaceable beam window. The subcritical core design implies a lot of investigations on the homogeneity of the neutron flux, the burn up reactivity swing, the criticality control and the in-core actinide fuel management. Dedicated transmutation facilities will have to be erected near the large reprocessing plants in order to reduce as much as possible fuel recycling and transportation of highly radioactive materials. Development of dedicated transmutation facilities may take at least 25 years to reach the mature industrial level. The operation of a combined P and T prototype facility on a single site may possibly start in the second quarter of the 21st century