Disposal of irradiated graphite (CarboDISP). Final report

In the project 0258790 the following results were obtained: Estimation of the amount of irradiated nuclear graphite (i-graphite) in Germany and characterization of selected samples of nuclear graphite. Investigation of distribution and localization of ¹⁴C and other radionuclides in irradiated graphite by means of modern microscopic and chemical methods; complimentary simulations of ¹⁴C-activation, -distribution and radionuclide inventory in the gas phase over irradiated nuclear graphite using theoretical MCNP models. Determination of ¹⁴C-release rates from irradiated graphite on different repository relevant conditions. Investigation of interaction between irradiated graphite and geopolymers (used as a binder material) under conditions relevant to final disposal. Statement of important criteria for treatment of irradiated graphitic wastes under conditions relevant for final disposal KONRAD. Thereby, the goals of the project have been fulfilled. Especially the education of young academics and their national and international integration into the scientific network was pushed forward. The CarboDisp project was carried out in a close collaboration with MEPhI (Moscow Engineering Physics Institute, Russian Federation), which contributed to the reinforcement of the future cooperation. The project has made a significant contribution to the training of young scientists and has thus contributed to the growth and maintenance of competence in the field of graphite waste treatment, in particular, to the issue of safe and sustainable nuclear waste management.