ITER tritiated waste management by the Host state and first lessons learned for fusion development

Abstract This paper summarises the present status of the ITER tritiated waste management strategy under development in France. This paper describes the specific challenges posed by this radioactive waste containing tritium as well as the solutions planned for the various waste categories and the implementation expected for the ITER tritiated waste, including the features of the future interim storage facility called INTERMED. Several options to reduce temporary storage duration as well as to minimise out-gassing rates and tritium discharges into the environment are under study, the related issues and the preliminary results obtained are shown. The first lessons learned for fusion development and their extrapolation to future reactors are outlined based on four parameters: materials, operating temperature, fuel cycle efficiency and tritium removal technologies.