Technology Development for Radioactive Waste Disposal
For the safe disposal of radioactive waste materials, it is essential to accurately estimate the amount of exposure to be expected over long periods of time.
JGC has carried out experimental studies to gain migratory property data on radioactive nuclides and the analysis of environmental migration phenomena by developing simulations techniques. JGC, in from its a solid position in the area of radioactive wastes disposal, makes its technical know-how and expertise available for the assessment of toxic wastes.
- Simulation of underground geological conditions by use of an inert gas glove box (O2 concentration < 1ppm)
- Data Acquisition for migration of radioactive nuclides and toxic substances and radioactive nuclide
- Diffusion coefficient, Distribution coefficient (Kd), solubility, and permeability coefficient
- Transformation of artificial barrier materials
- Simulations for the migration of radioactive nuclides and toxic substances and radioactive nuclides
- Leaching rate from simulated radioactive wastes
- Distribution coefficient on artificial barrier materials (cement mortar, cement concrete, bentonite, etc.)
- Diffusion coefficient in artificial barrier materials
- Hydraulic permeability coefficient in bentonite
- Transformation phenomena of bentonite by underground water flow
- Melting and testing facility for iodine-immobilized glass (BPI glass)