Effect of Cement on Radioactive Waste-Form Performance in Multicomponent Systems Tests at 200 C

Abstract

The release of cesium-137, strontium-90, plutonium-239 and 240, americium-241 and curium-244 from used fuel and a fuel recycle waste glass has been investigated in the presence of either cement or granite, Ga-bentonite, Inconel 625 and saline groundwater at 200 degrees C, 8.5 MPa. It was found that cesium and strontium sorb preferentially onto the clay whereas the actinides sorb mainly onto the cement. Cement-glass interaction appears to lead to accelerated alteration of the glass compared with a multicomponent system without cement present. The dissolution rate of used fuel is not affected by the cement.