Bituminised Waste Re-treatment: Replacement of the Bitumen Matrix by a Glass Matrix
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Abstract
The vitrification of nuclear waste salts similar to the salts present in Eurobitum produced by the former Eurochemic reprocessing plant, Mol-Dessel, Belgium, is investigated. In order to approach the composition of the high-level waste reference glass SON68, mixtures with different ratios of glass frit to waste salts have been prepared and vitrified. The concentration of the waste salts varied between 17 and 25 % by weight.
To compare the short term corrosion behaviour with reference waste glass, leach tests have been performed. The results are compared with similar leaching tests on R7T7 type SON68 glass. Most elements are better retained in the simulated Eurobitum glass than in the SON68 glass.
Details
| Original language | English |
|---|---|
| Title of host publication | Scientific Basis for Nuclear Waste Management XXIX |
| Place of Publication | Warrendale, PA, Belgium |
| Pages | 743-750 |
| Volume | 1 |
| Publication status | Published - Jun 2006 |
| Event | 29th International Symposium on the Scientific Basis for Nuclear Waste Management - Ghent, Belgium Duration: 12 Sep 2005 → 16 Sep 2005 |
Publication series
| Name | MRS Proceedings |
|---|---|
| Number | Volume 932 |
Conference
| Conference | 29th International Symposium on the Scientific Basis for Nuclear Waste Management |
|---|---|
| Country | Belgium |
| City | Ghent |
| Period | 2005-09-12 → 2005-09-16 |
Keywords
- Bituminised waste, vitrification, R7-T7
ID: 345843