Nuclear waste glass interfaces after one year burial in STRIPA. Pt. 1

Two simulated nuclear waste glasses were corroded in an in-situ experiment in the STRIPA mine up to one year at 900C. Changes in compositional in-depth profiles for glass/glass interfaces were measured using SIMS. Both glasses showed a depletion of Na, Cs, and B, but for the more corrosion resistant glass, the lower depletion depth is ascribed to the formation of a thin (2.0 m) coherent and dense outer layer, enriched in Mg, Ca, Sr, Ba, Zn-Al, Fe, and Si, which impedes both the ion exchange and network attack of the bulk glass underneath. (orig.)