Diffusion of uranium in compacted bentonites in the reducing condition with corrosion products of iron
Book
·
OSTI ID:264473
- Kyushu Univ., Fukuoka (Japan). Dept. of Nuclear Engineering
In high-level waste repository, a carbon steel overpack will be corroded after closure. This will create a reducing environment in the vicinity of the repository. Reducing conditions are expected to retard the migration of redox-sensitive radionuclides such as uranium. The apparent diffusion coefficients of uranium were measured in compacted bentonites (Kunigel V1{reg_sign} and Kunipia F{reg_sign}, JAPAN) in contact with carbon steel and its corrosion products under reducing conditions or without carbon steel under oxidizing conditions for comparison. The apparent diffusion coefficients measured were 10{sup {minus}12} to 10{sup {minus}14} m{sup 2}/s under oxidizing conditions and 10{sup {minus}13} to 10{sup {minus}14} m{sup 2}/S under reducing conditions. There were significant effects of redox conditions, dry density (0.8 to 2.0 g/cm{sup 3}) and montmorillonite contents (60% for Kunigel V1 or 100% for Kunipia F) on the apparent diffusion coefficients. The sorption of uranium on corrosion products of iron was smaller than that on montmorillonite. Montmorillonite density could be a good index to explain density dependence of the diffusion coefficients under the reducing conditions. Uranium would diffuse in free pore water with diffusion coefficients greater than 10{sup {minus}13} m{sup 2}/s in low density bentonites under both redox conditions because the diffusion coefficients depended on sorption coefficients. Since diffusion coefficients were independent of sorption coefficients in high density bentonites where free pore water is scarce, surface diffusion might occur with coefficients were of about 10{sup {minus}13} m{sup 2}/s.
- OSTI ID:
- 264473
- Report Number(s):
- CONF-951155--; ISBN 1-55899-315-0
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
05 NUCLEAR FUELS
36 MATERIALS SCIENCE
BACKFILLING
BENTONITE
CARBON STEELS
CORROSION PRODUCTS
DIFFUSION
EXPERIMENTAL DATA
HIGH-LEVEL RADIOACTIVE WASTES
JAPAN
PERMEABILITY
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE FACILITIES
RADIONUCLIDE MIGRATION
REDOX REACTIONS
SORPTION
SORPTIVE PROPERTIES
URANIUM
36 MATERIALS SCIENCE
BACKFILLING
BENTONITE
CARBON STEELS
CORROSION PRODUCTS
DIFFUSION
EXPERIMENTAL DATA
HIGH-LEVEL RADIOACTIVE WASTES
JAPAN
PERMEABILITY
RADIOACTIVE WASTE DISPOSAL
RADIOACTIVE WASTE FACILITIES
RADIONUCLIDE MIGRATION
REDOX REACTIONS
SORPTION
SORPTIVE PROPERTIES
URANIUM