Nations producing borosilicate glass as an immobilization material for radioactive wastes resulting from spent nuclear fuel reprocessing have reinforced scientific collaboration to obtain consensus on mechanisms controlling the long-term dissolution rate of glass. This goal is deemed to be crucial for the development of reliable performance assessment models for geological disposal. The collaborating laboratories all conduct fundamental and/or applied research with modern materials science techniques. The paper briefly reviews the radioactive waste vitrification programmes of the six participant nations and summarizes the state-of-the-art of glass corrosion science, emphasizing common scientific needs and justifications for on-going initiatives.
Revised: September 23, 2013 |
Published: June 8, 2013
Citation
Gin S., A. Abdelouas, L.J. Criscenti, W.L. Ebert, K. Ferrand, T. Geisler, and M.T. Harrison, et al. 2013.An international initiative on long-term behavior of high-level nuclear waste glass.Materials Today 16, no. 6:243-248.PNNL-SA-97248.doi:10.1016/j.mattod.2013.06.008