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In order to develop glass formulation for vitrifying combustible dry active waste (DAW) generated from nuclear power plants of Korea Hydro & Nuclear Power (KHNP) Co., Ltd., promising glass formulation was selected based on glass property model predictions for viscosity, electrical conductivity and leach resistance. Laboratory measurements were conducted to verify the model predictions. Based on the results, the models for viscosity, electrical conductivity, and 7-day product consistency test (PCT) elemental release are accurate for the DAW glass formulation. The glass formulation meets all the KHNP glass property constraints, and use of this glass formulation on the pilot scale was conducted successfully. The process parameters were in the desired ranges. The product quality such as chemical durability, phase stability, etc., was satisfactory.

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Chromium oxide (Cr 2 O 3 ) solubility was measured in soda lime borosilicate glass from 1400 to 1500 K. The temperature dependence of the solubility increased with increased sodium oxide concentration. The enthalpies of solution for the equilibrium phases were calculated from the solubility data in the temperature range from 1400 to 1500 K. The enthalpy of fusion for Cr 2 O 3 at 1450 K was calculated to be 108.0 kJ⅐mol ؊1 . This value was less than our measured values for enthalpy of solution, 111.0 ؎ 0.5 and 158.4 ؎ 0.3 kJ⅐mol ؊1 , indicating that all enthalpies of mixing were positive; that is, the mixing process was endothermic. This characterized the interaction between solute and solvent as repulsive.

The Ulchin Vitrification Facility (UVF), to be used for the vitirification of low- and intermediate-level radioactive waste (LILW) generated by nuclear power plants (NPPs), is the world’s first commercial facility using Cold Crucible Induction Melter (CCIM) technology. The construction of the facility was begun in 2005 and was completed in 2007. From December 2007 to September 2009, all key performance tests, such as the system functional test, the cold test, the hot test, and the real waste test, were successfully carried out. The UVF commenced commercial operation in October 2009 for the vitrification of radioactive waste.