Interaction of cementitious materials with high-level waste matrices

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Abstract

The paper discusses the expected evolution of the interface between the waste form and the near field in the case of disposal following the Supercontainer Design, and the main mechanisms of radionuclide release by the waste forms and how they are expected to be influenced by the concrete of the Supercontainer. The related experimental programme and its first results are presented. The Supercontainer conditions probably increase the radionuclide release rate from vitrified waste, compared to bentonite based engineered barrier system, because of pump effect by secondary phase formation at high pH. A decrease of dissolution rate possible only if pH at the glass surface decreases with time. This is likely but difficult to quantify. The high pH of Supercontainer conditions seems to have relatively little effect on the long term fuel stability, but some potential problems (alpha threshold, colloid formation, difference between UO2 and spent fuel, impact of sorption on concrete) must be investigated more in detail.

Details

Original languageEnglish
Title of host publicationCementitious materials in safety cases for geological repositories for radioactive waste: role, evolution and interaction
Place of PublicationParis, France
Pages129-130
Publication statusPublished - Mar 2012
EventCementitious Materials in Safety Cases for Geological Repositories for Radioactive Waste: Role, Evolution and Interactions - NEA IGSC, Brussels, Belgium
Duration: 17 Nov 200920 Nov 2009

Publication series

NameNEA/RWM report
NumberNEA/RWM/R(2012)3

Conference

ConferenceCementitious Materials in Safety Cases for Geological Repositories for Radioactive Waste: Role, Evolution and Interactions
Country/TerritoryBelgium
CityBrussels
Period2009-11-172009-11-20

Keywords

  • concrete, cement, high-level waste, disposal, Supercontainer

ID: 187809