The strategy of the Belgian nuclear research centre in the area of high level waste form compatibility research

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Abstract

The Belgian Nuclear Research Centre (SCK·CEN) has a long-standing expertise in research concerning the compatibility of waste forms with the final disposal environment. For high level waste, most attention goes to two waste forms that are relevant for Belgium, namely (1) vitrified waste from the reprocessing of spent fuel, and (2) spent fuel as such, referring to the direct disposal scenario. The final objective of these studies, is to estimate the contribution of the waste form to the overall safety of the disposal system, as part of the Safety and Feasibility Case, planned by the national agency ONDRAF/NIRAS. The recent change of the Belgian disposal concept from an engineered barrier system based on the use of bentonite clay to a system based on a concrete buffer has caused a reorientation of the research programme. The paper explains the current R&D approach, and highlights some recent experimental set-ups available at SCK•CEN for this purpose, with some illustrating results.

Details

Original languageEnglish
Title of host publicationThe 11th International Conference on Environmental Remediation and Radioactive Waste Management
Place of PublicationFairfield, NJ, United States
Pages1-8
Publication statusPublished - May 2008
EventICEM 2007 - 11th International Conference on Environmental Remediation and Radioactive Waste Management - American Society of Mechanical Engineers (ASME), Bruges, Belgium
Duration: 2 Sep 20076 Sep 2007

Conference

ConferenceICEM 2007 - 11th International Conference on Environmental Remediation and Radioactive Waste Management
CountryBelgium
CityBruges
Period2007-09-022007-09-06

Keywords

  • borosilicate glass, corrosion, leaching, silica, clays, bentonite, sorption, diffusion, spent fuel, alteration, disposal

ID: 265592