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Integration of waste package characteristics
Present situation and main results of waste form
3 other sections not shown
activity backfill barrier system bitumen Cadarache CEA/Centre d'Etudes Nucléaires cesium clay concrete container corrosion Cumulative Fraction Release Département diffusion disposal conditions disposal facility disposal of radioactive drums effects engineered barriers equilibrium EUREX evaluation Evaporator Concentrate Fontenay-aux-Roses Full scale leaching function geological Gorleben homogeneous in-situ investigated ion exchange resins irradiation Konrad laboratory leach rate leach test leachability leachant leaching behaviour leaching experiments leaching mechanisms leaching resistance limit long-term low-level waste lysimeter Magnox matrix matrix materials NaCl Nuclear Regulatory Commission nuclides parameters performed permeability polymers pore pozzolanic properties Q-brine radioactive wastes radionuclide release radionuclides reactor release mechanisms Release of Cs-137 release rate repository requirements risk analysis safety assessment samples SESSION shallow land burial sludges Sodium sulfate solubility sorption source term specific specimens stability storage strontium surface swelling temperature transport waste form waste package Waste Solidified waste type wastes containing water uptake