Results of 16 Years of Testing of Vitrified Intermediate-Level Wastes from the Kursk Nuclear Power Plant

Autor: Dmitriev, S. A., Barinov, A. S., Ozhovan, N. V., Startseva, I. V., Golubeva, Z. I., Sobolev, I. A., Ozhovan, M. I.
Zdroj: Atomic Energy; March 2005, Vol. 98 Issue: 3 p196-201, 6p
Abstrakt: 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.
Databáze: Supplemental Index