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 and studies of CCS (Carbon Capture, Transport & Sequestration).

Inert gas glove box
Inert gas glove box
Hydraulic permeability test unit
Hydraulic permeability test unit

Features

  • Simulation of underground geological conditions by use of an inert gas glove box (O2 concentration < 1ppm)
  • Various Experiment experiments using radioactive nuclides (R1)

Applications

  • Data Acquisition for migration of radioactive nuclides and toxic substances and radioactive nuclide
    • Diffusion coefficient, Distribution coefficient (Kd), solubility, and permeability coefficient
    • Transformation of barrier materials
  • Simulations for the migration of radioactive nuclides and toxic substances and radioactive nuclides

Assessment Experience

  • Leaching rate from simulated radioactive wastes
  • Distribution coefficient on barrier materials (cement mortar, cement concrete, bentonite, etc.)
  • Diffusion coefficient in barrier materials
  • Hydraulic permeability coefficient in bentonite
  • Transformation phenomena of bentonite by underground water flow