DISPERSION AND SORPTION CHARACTERISTICS OF URANIUM IN THE ZEOLITE-QUARTZ MIXTURE AS BACKFILL MATERIAL IN THE RADIOACTIVE WASTE REPOSITORY

https://doi.org/10.22146/ijc.21729

Herry Poernomo(1*), Noor Anis Kundari(2)

(1) Centre for Accelerator and Material Process Technology, Babarsari Street P.O. Box 6101 Ykbb Jogjakarta 55281
(2) Polytechnic Institute of Nuclear Technology, National Nuclear Energy Agency, Babarsari Street P.O. Box 6101 Ykbb Jogjakarta 55281
(*) Corresponding Author

Abstract


The experiment of sorption and dispersion characteristics of uranium in the zeolite-quartz mixture as candidate of raw material of backfill material in the radioactive waste repository has been performed. The objective is to know the effect of zeolite and quartz grain size on the zeolite-to-quartz weight ratio that gives porosity (ε), permeability (K), and dispersivity (α) of uranium in the zeolite-quartz mixture as backfill material. The experiment was carried out by fixed bed method in the column filled by the zeolite-quartz mixture with zeolite-to-quartz weight percent ratio of 100/0, 80/20, 60/40, 40/60, 20/80, 0/100 wt. % in the water saturated condition flowed by uranyl nitrate solution of 500 ppm concentration (Co) as uranium simulation which was leached from immobilized radioactive waste in the repository. The concentration of uranium in the effluents represented as Ct were analyzed by spectrophotometer Corning Colorimeter 253 every 15 minutes, then using Co and Ct uranium dispersivity (α) in the backfill material was determined. The experiment data shown that 0.196 mm particle size of zeolite and 0.116 mm particle size of quartz on the zeolite-to-quartz weight ratio of 60/40 wt. % with ε = 0.678, K = 3.345x10-4 cm/second, and α = 0.759 cm can be proposed as candidate of raw material of backfill material in the radioactive waste repository.


Keywords


backfill material; quartz; radioactive waste; zeolite

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References

[1] Lopez, R.S. and Johnson, L.H., 1986, Vault Sealing Research and Development for the Canadian Nuclear Fuel Waste Management, Atomic Energy of Canada Limited, 9053.

[2] LeNeveu, D.M., 1986, Vault Submodel for the Second Interim Assesment of the Canadian Concept for Nuclear Fuel Waste Disposal : Post-Closure Phase, Atomic Energy of Canada Limited - 8383.

[3] Aoki, M.M.M, Takizawa, M. and Takahashi, M., 1984, Waste Management 2, 495-501.

[4] Miyahara, K. and Sasaki, N., 1991, Radiochem. Acta 52/53, 293-297.

[5] Conca, J.L., Ashida, T., and Sato, H., 1991, Waste Management 2, 1382-1389.

[6] Kanwar, R., and Wattal, P.R., 1983, Conditioning of Law Heat Generating Waste by Incorporation in Barrier Impregnated Composite Matrice, A Review of Experience in Industrial Scale Operation, Proceeding of Symposium Utrecht, IAEA, Vienna.

[7] Verstricht, J., Demarche, M., and Gatabin, C., 2001, Development of Backfill Material within the Belgium Concept for Geological Disposal of High-Level Radioactive Waste : An Example of Successful International Co-operation, Waste Management Conceference, Tucson Arizona.

[8] Martini, T., 1999, Zeolit, Dinas Pertambangan, Pemda Daerah Istimewa, Yogyakarta.

[9] Poernomo, H., Sardjono, D., and Budiyono, M.E., 2004, Sorption and Difusion Characteristics of 90Sr in the Coal Ash as Backfill Material Candidate on the Radioactive Waste Repository, Proceeding of XIV Chemistry National Seminar, Gadjah Mada University, Yogyakarta.

[10] Ven Te Chow, 1964, Handbook of Applied Hidrology, Mc Graw-Hill Book Company, New York, pp. 13-1, 13-15.

[11] Champ, D.R., Moltyaner, G.L., Young, J.L. and Lapcevic, P., 1985, A Downhole Column Technique for Filed Measurement of Transport Parameter, AECL-8905.

[12] Schneider, K., 1982, Site Investigation for Repositories for Solid Radioactive Wastes in Shallow Ground, Technical Report Series No. 216, Vienna.

[13] Guven, R.W., 1985, Water Resource Research 21,5.

[14] Wiederhold, E.W., 1972, Use of Local Minerals in the Treatment of Radioactive Waste, Technical Report Series No. 136, IAEA, Vienna.



DOI: https://doi.org/10.22146/ijc.21729

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