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 languageEnglish
Title of host publicationScientific Basis for Nuclear Waste Management XXIX
Place of PublicationWarrendale, PA, Belgium
Pages743-750
Volume1
Publication statusPublished - Jun 2006
Event29th International Symposium on the Scientific Basis for Nuclear Waste Management - Ghent, Belgium
Duration: 12 Sep 200516 Sep 2005

Publication series

NameMRS Proceedings
NumberVolume 932

Conference

Conference29th International Symposium on the Scientific Basis for Nuclear Waste Management
CountryBelgium
CityGhent
Period2005-09-122005-09-16

Keywords

  • Bituminised waste, vitrification, R7-T7

ID: 345843