SORPTION AND DISPERSION OF STRONTIUM RADIONUCLIDE IN THE BENTONITE-QUARTZ-CLAY AS BACKFILL MATERIAL CANDIDATE ON RADIOACTIVE WASTE REPOSITORY

Herry Poernomo

doi:10.22146/ijc.21430

SORPTION AND DISPERSION OF STRONTIUM RADIONUCLIDE IN THE BENTONITE-QUARTZ-CLAY AS BACKFILL MATERIAL CANDIDATE ON RADIOACTIVE WASTE REPOSITORY

https://doi.org/10.22146/ijc.21430

Herry Poernomo^(1*)

(1) Centre for the Accelerator and Material Process Technology National Nuclear Energy Agency, Jl. Babarsari P.O. Box 6101 Ykbb Yogyakarta 55281
(*) Corresponding Author

Abstract

The experiment of sorption and dispersion characteristics of strontium in the mixture of bentonite-quartz, clay-quartz, bentonite-clay-quartz as candidate of raw material for backfill material in the radioactive waste repository has been performed. The objective of this research is to know the grain size effect of bentonite, clay, and quartz on the weight percent ratio of bentonite to quartz, clay to quartz, bentonite to clay to-quartz can be gives physical characteristics of best such as bulk density (r_b), effective porosity (e), permeability (K), best sorption characteristic such as distribution coefficient (K_d), and best dispersion characteristics such as dispersivity (a) and effective dispersion coefficient (D_e) of strontium in the backfill material candidate. The experiment was carried out in the column filled by the mixture of bentonite-quartz, clay-quartz, bentonite-clay-quartz with the weight percent ratio of bentonite to quartz, clay to quartz, bentonite to clay to quartz of 100/0, 80/20, 60/40, 40/60, 20/80, 0/100 respectively at saturated condition of water, then flowed 0.1 N Sr(NO₃)₂ as buffer solution with tracer of 0.05 Ci/cm³⁹⁰Sr as strontium radionuclide simulation was leached from immobilized radioactive waste in the radioactive waste repository. The concentration of ⁹⁰Sr in the effluents represented as C_t were analyzed by Ortec b counter every 30 min, then by using profile concentration of C_o and C_t, values of K_d, a and D_e of ⁹⁰Sr in the backfill material was determined. The experiment data showed that the best results were -80+120 mesh grain size of bentonite, clay, quartz respectively on the weight percent ratio of bentonite to clay to quartz of 70/10/20 with physical characteristics of r_b = 0.658 g/cm³, e = 0.666 cm³/cm³, and K = 1.680x10^-2 cm/sec, sorption characteristic of K_d = 46.108 cm³/g, dispersion characteristics of a = 5.443 cm, and D_e = 1.808x10^-03 cm²/sec can be proposed as candidate of raw material of backfill material in the radioactive waste repository.

Keywords

sorption; dispersion; strontium; backfill material

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DOI: https://doi.org/10.22146/ijc.21430