Matrix material for embedding and intermediate and/or final storage of radioactive waste, comprises graphite, which is natural graphite and/or synthetic graphite, and inorganic binder, which is a borosilicate glass

摘要

The matrix material for embedding and intermediate and/or final storage of radioactive waste (3, 4, 5, 6), comprises graphite that is natural graphite (60-100 wt.%) (1) and/or synthetic graphite (0-40 wt.%) (1a), and an inorganic binder (15-25 wt.%) (2), which is a borosilicate glass and is a graphite-wetted material in melted and/or molten state. The graphite comprises irradiated, radiated and radioactive contaminated graphite. A pressing additive is mixed to the matrix material and carbon and/or graphite is mixed to the matrix material in the form of fibers.