The role of Al2O3 in the long-term corrosion stability of nuclear waste glasses

摘要: Abstract The corrosion stability of borosilicate waste glasses has been investigated, as a function the AlO 1.5 (in balance with SiO 2 ) content. content ranged from 6.7 to 18.2 mol%. Surface area solution volume ( SA/V values 100, 500, 2500 and 10000 m −1 , temperatures 90 150°C were considered. High T especially used accelerate corrosion. leaching medium was distilled water, total durations up 600 days, tests interpreted in terms composition either without or after ultrafiltration. data reveal that long term dissolution soluble elements B, Na Li is diffusion-controlled for all glasses. appears be meaningful accelerating parameter. glass determines sequence kind processes, but final are not different. “final” experimental B range between 700 1050 mgl at 90°C (105 days ), 19000 56000 (400 ).