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JGC has achieved safety assessment studies and design of radioactive waste disposal sites. As it is essential to estimate the residents' radioactive exposure for a span of more than 100,000 years, JGC has carried out experimental studies to gain migratory property data on radioactive nuclides and analysis environmental migration phenomena by developing simulations techniques.
JGC, in a solid position in the area of radioactive wastes disposal, makes its technical know-how and expertise available for assessment of toxic wastes and studies of CCS (Carbon Capture, Transport & Sequestration). |
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Features |
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- Simulation of underground geological conditions by use of an inert gas glove box
(O2 concentration < 1 ppm)
- Experiment using radioactive nuclides. (except Pu)
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Inert gas glove box |
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| Hydraulic permeability test unit |
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| Applications |
- Data Acquisition for migration of toxic substances and radioactive nuclide
- Diffusion coefficient, Distribution coefficient (Kd), solubility, and permeability coefficient
- Transformation of barrier materials
- Simulations for migration of toxic substances and radioactive nuclides
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Assessment Experience |
- Leaching rate from simulated radioactive wastes
- Distribution coefficient on barrier materials (cement mortal, cement concrete, bentonite, etc.)
- Diffusion coefficient in barrier materials
- Hydraulic permeability coefficient in bentnite
- Transformation phenomena of bentonite by underground water flow
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