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J. Korean Ceram. Soc. > Volume 40(10); 2003 > Article
Journal of the Korean Ceramic Society 2003;40(10): 936.
doi: https://doi.org/10.4191/kcers.2003.40.10.936
Glass Formulations for Vitrification of Low- and Intermediate-level Waste
Cheon-Woo Kim, Jong-Kil Park, Jong-Hyun Ha, Myung-Jae Song, Nel-Son Lee1, Peter-C. Kong1, Gary-L. Anderson1
Nuclear Environment Technology Institute, Korea Hydro & Nuclear Power Co., Ltd.
1Idaho National Engineering and Environmental Laboratory Idaho Falls
ABSTRACT
In order to develop glass formulations for vitrifying Low-and Intermediate-Level radioactive Wastes (LILW) from nuclear power plants of Korea Hydro & Nuclear Power (KHNP) Co., Ltd., promising glass formulations were 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 electrical conductivity, US DOE 7-day Product Consistency Test (PCT) elemental release, and pH of PCT leachate are accurate for the LILW glass formulations. However, the model for viscosity was able to provide only qualitative results. A leachate conductivity test was conducted on several samples to estimate glass leach resistance. Test results from the leachate conductivity test were useful for comparison before PCT elemental release results were available. A glass formulation K11A meets all the KHNP glass property constraints, and use of this glass formulation on the pilot scale is recommended. Glass formulations K12A, K12B, and K12E meet nearly all of the processing constraints and may be suitable for additional testing. Based on the comparison between the measured and predicted glass properties, existing glass property models may be used to assist with the LILW glass formulation development.
Key words: Low- and Intermediate-Level radioactive Waste (LILW), Glass formulation, Viscosity, Electrical conductivity, PCT
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