Diffusion of radionuclides in compacted bentonite: Results from combined glass dissolution and migration tests

Conference · Sun Dec 31 04:00:00 EST 1995

OSTI ID:377929

Tsukamoto, Masaki; Ohe, T; Fujita, T ^[1]; Hesboel, R ^[2]; Hermansson, H P ^[3]

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1. Central Research Inst. of Electric Power Industry, Komae, Tokyo (Japan)
2. Studsvik Radwaste AB, Nykoeping (Sweden)
3. Studsvik Material AB, Nykoeping (Sweden)

Diffusion experiments of radionuclides in compacted sodium bentonite with a dry density of 1.0 g/cm{sup 3} were performed i nitrogen gas atmosphere at 90 C for 208 d and 375 d. The corrosion experiments of crushed radioactive glass, JSS-A, carried out simultaneously to provide the source of the radionuclides for the diffusion experiments. The normalized elemental mass losses of cesium isotopes and {sup 238}Pu were lower than those of boron (ca. 10 g/m{sup 2}) probably because of the difference of sorption and/or precipitation. The apparent diffusion coefficient of {sup 238}Pu, {sup 234}U and {sup 125}Sb were determined to be 2 {times} 10{sup {minus}14} m{sup 2}/s, 5 {times} 10{sup {minus}12} m{sup 2}/s and 2 {times} 10{sup {minus}12} m{sup 2}/s, respectively. The distribution coefficient of Pu estimated from the diffusion data was of the same order as that from batch sorption experiments. The glass corrosion and the plutonium diffusion were described by the geochemical codes PHREEQE, STRAG4 and GESPER. The calculation results well fitted the observed data.

• OSTI ID: 377929
• Report Number(s): CONF-941075--; ISBN 1-55899-253-7
• Country of Publication: United States
• Language: English

Related Subjects

05 NUCLEAR FUELS
36 MATERIALS SCIENCE
ANTIMONY 125
BENTONITE
BORON
BULK DENSITY
CESIUM ISOTOPES
COMPUTERIZED SIMULATION
CORROSION
DIFFUSION
G CODES
GEOCHEMISTRY
GLASS
HIGH-LEVEL RADIOACTIVE WASTES
LEACHATES
P CODES
PLUTONIUM 238
RADIOACTIVE WASTE DISPOSAL
RADIONUCLIDE MIGRATION
S CODES
UNDERGROUND DISPOSAL
URANIUM 234
WASTE FORMS