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J Radiat Prot > Volume 29(1); 2004 > Article
Journal of Radiation Protection 2004;29(1):33-0.
Studies on the Physico-chemical Properties of Mixed Radioactive Waste Glass
Kim, C.W.;Choi, J.R.;Ji, P.K.;Park, J.K.;Shin, S.W.;Ha, J.H.;Song, M.J.;Hwang, T.W.;Park, S.J.;
In order to vitrify the W1 waste (ion-exchange resin(IER), zeolite, and dry active waste(DAW)) generated from Korean Nuclear Power Plants, a glass formulation development based on waste compositions and production rates was performed. A aluminoborosilicate glass, AG8W1, was formulated to vitrify the W1 waste in an induction cold crucible melter(CCM). The processability, product performance, and economics of the candidate glass were calculated using a computer code and were measured experimentally in the laboratory and CCM. The glass viscosity and electrical conductivity as the process parameters were in the desired ranges. Start-up and maintaining glass melt of the candidate glass were favorable in the CCM. The product quality of the glass such as chemical durability, phase stability, etc. was satisfactory. The vitrification process using the candidate glass was also evaluated to be operated as economically as possible.
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