Abstract
Data from a field experiment performed over a period of 16 years at the testing site of the Moscow Scientific and Industrial Association Radon, studying intermediate-level activity K-26 glass with surface storage, are analyzed. The average 137Cs leach rate was 2.2·10−7 g/(cm2·day) over 16 years of testing. The effective mutual diffusion coefficient of cesium was found to be 5·10−21 m2/sec and the rate of hydrolysis of the glass framework was found to be 0.1 µm/yr. The calculation showed that the maximum possible amount of leached radionuclides from glass does not exceed 20 kBq over 300 yr.
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Translated from Atomnaya Energiya, Vol. 98, No. 3, pp. 206–211, March, 2005.
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Dmitriev, S.A., Barinov, A.S., Ozhovan, N.V. et al. Results of 16 Years of Testing of Vitrified Intermediate-Level Wastes from the Kursk Nuclear Power Plant. At Energy 98, 196–201 (2005). https://doi.org/10.1007/s10512-005-0193-7
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DOI: https://doi.org/10.1007/s10512-005-0193-7