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ISSN : 1738-1894(Print)
ISSN : 2288-5471(Online)
Journal of Nuclear Fuel Cycle and Waste Technology Vol.2 No.3 pp.175-180
DOI :

방사성폐기물 유리화 공정 및 유리고화체 특성

Characteristics of Vitrification Process and Vitrified Form for Radioactive Waste

Cheon-Woo Kim, Ji-Yean Kim, Jong-Rak Choi, Pyung-Kook Ji, Jong-Kil Park, Sang-Woon Shin, Jong-Hyun Ha, Myung-Jae Song

Abstract

In order to vitrify the combustible dry active waste (DAW) generated from Korean Nuclear Power Plants, a glass formulation development based on waste composition was performed. A borosilicate glass, DG-2, was formulated to vitrify the DAW in an induction cold crucible melter (CCM). The processability, product performance, and volume reduction effect of the candidate glass were evaluated 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 of the glass product such as chemical durability, phase stability, and density was satisfactory. The vitrification process using the candidate glass was also evaluated assuming that it was operated as economically as possible.

 

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