핵폐기용 모의글라스의 조성변화에 따른 용출특성에 관한 연구
In order to manufacture an attractive waste glass for the permanent and secure disposal of high-level radioactive waste, the complex composition of the simulated nuclear waste glass PNL-7668 was simplified to a composition of sodium borosilicate glass. The substitutions of $Fe_2O_3$ and $Al_2O_3$ we...
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| Published in | Biuletyn Uniejowski Vol. 28; no. 5; pp. 259 - 266 |
|---|---|
| Main Authors | , , , |
| Format | Journal Article |
| Language | Korean |
| Published |
한국표면공학회
1995
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| Online Access | Get full text |
| ISSN | 1225-8024 2299-8403 |
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| Abstract | In order to manufacture an attractive waste glass for the permanent and secure disposal of high-level radioactive waste, the complex composition of the simulated nuclear waste glass PNL-7668 was simplified to a composition of sodium borosilicate glass. The substitutions of $Fe_2O_3$ and $Al_2O_3$ were added to examine on the leaching characteristics of simulated nuclear waste glass with variable composition. The leach tests for these glasses were performed according to 'MCC-1, Static Leach Test Procedure' in acid and basic solution. In this study, for the $Al_2O_3$-containing glasses, Na ion release from these glasses was higher in acid solution than in basic solution. As the content of $Fe_2O_3$ was increased in glasses, Na ion release was increased in acid solution, in spite of decrease of amount of total mass diminution. |
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| AbstractList | In order to manufacture an attractive waste glass for the permanent and secure disposal of high-level radioactive waste, the complex composition of the simulated nuclear waste glass PNL-7668 was simplified to a composition of sodium borosilicate glass. The substitutions of $Fe_2O_3$ and $Al_2O_3$ were added to examine on the leaching characteristics of simulated nuclear waste glass with variable composition. The leach tests for these glasses were performed according to 'MCC-1, Static Leach Test Procedure' in acid and basic solution. In this study, for the $Al_2O_3$-containing glasses, Na ion release from these glasses was higher in acid solution than in basic solution. As the content of $Fe_2O_3$ was increased in glasses, Na ion release was increased in acid solution, in spite of decrease of amount of total mass diminution. |
| Author | 류수착(S. C. Ryu) 한호현(H. H. Han) 이승한(S. H. Lee) 류봉기(B. K. Ryu) |
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| StartPage | 259 |
| Title | 핵폐기용 모의글라스의 조성변화에 따른 용출특성에 관한 연구 |
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