We report analysis of chemical durability of UK HLW MW+25% simulant glass under model hyperalkaline conditions of a colocated geological disposal facility. Glass powders and monoliths were dissolved for 168 days in saturated Ca(OH). Dissolution in the presence of high c... View more
2. Development of the Nirex Reference Vault Backfill; Report on Current Status in 1994. United Kingdom Nirex Ltd. Report number S/97/014, 1997.
3. Geological Disposal: Generic Environmental Safety Case Main Report. Nuclear Decommissioning Authority report, NDA/RWMD/021, 2010.
4. P. K. Abraitis, B. P. McGrail, D. P. Trivedi, F. R. Livens, and D. J. Vaughan, “Single-Pass Flow-Through Experiments on a Simulated Waste Glass in Alkaline Media at 40 °C: I. Experiments Conducted at Variable Solution Flow Rates to Glass Surface Area Ratio,” J. Nucl. Mat., 280 196-205 (2000).
5. S. Gin and J. P. Mestre, “SON 68 Nuclear Glass Alteration Kinetics Between pH 7 and pH 11.5,” J. Nucl. Mat., 295 83-96 (2001).
6. E. M. Pierce, W. E. A. Rodriguez, L. J. Calligan, W. J. Shaw, and B. P. McGrail, “An Experimental Study of the Dissolution Rates of Stimulated Aluminoborosilicate Waste Glasses as a Function of pH and Temperature Under Dilute Conditions,” Appl. Geochem., 23 2559-2573 (2008).
7. Z. Andriambololona, N. Godon, and E. Vernaz, “Glass Alteration in the Presence of Mortar: Effect of the Cement Grade,” Proc. Mat. Sci. Symp., 257 151-158 (1992).
8. T. Chave, P. Frugier, S. Gin, and A. Ayral, “Glass-Water Interphase Reactivity with Calcium Rich Solutions,” Geochim. Cosmochim. Acta, 75 4125-4139 (2011).
9. C. A. Utton, R. J. Hand, P. A. Bingham, N. C. Hyatt, S. W. Swanton, and S. J. Williams, “Dissolution of Vitrified Wastes in a High-pH Calcium-Rich Solution,” J. Nucl. Mat., 435 112-122 (2013).
10. C. A. Utton, R. J. Hand, N. C. Hyatt, S. W. Swanton, and S. J. Williams, “Formation of Alteration Products During Dissolution of Vitrified ILW in a High-pH Calcium-Rich Solution,” J. Nucl. Mat., 442 33-45 (2013).