An experimental study of the dissolution rates of simulated aluminoborosilicate waste glasses as a function of pH and temperature under dilute conditions

Applied Geochemistry

Volumn 23, Issue 9, 2008, Pages 2559-2573

  Pierce, Eric M ^a   Rodriguez, Elsa A ^a   Calligan, L J ^b   Shaw, Wendy J ^a   Pete McGrail, B ^a  

^a PACIFIC NORTHWEST NATIONAL LABORATORY   (United States)

^b TEXAS SOUTHERN UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

DISSOLUTION RATES; EXPERIMENTAL STUDIES; FLOW-THROUGH TESTS; KINETIC RATE LAWS; WASTE GLASSES;

DISSOLUTION;

ALUMINOSILICATE; AQUEOUS SOLUTION; BORON; DILUTION; DISSOLUTION; EXPERIMENTAL STUDY; GLASS; IMMOBILIZATION; ION EXCHANGE; PH; WASTE;

PASSIFLORA;

EID: 50249120698     PISSN: 08832927     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.apgeochem.2008.05.006     Document Type: Article

References (75)

1. Åagaard P., and Helgeson H.C. Thermodynamic and Kinetic Constraints on Reaction Rates among Minerals and Aqueous Solutions. I. Theoretical Considerations. Am. J. Sci. 282 (1982) 237-285
2. Abraitis P.K., Livens F.R., Monteith J.E., Small J.S., Trivedi D.P., Vaughan D.J., and Wogelius R.A. The kinetics and mechanisms of simulated British Magnox waste glass dissolution as a function of pH, silicic acid activity, and time in low temperature aqueous systems. Appl. Geochem. 15 (2000) 1399-1416
3. Advocat, T., Crovisier, J.L., Fritz, B., Vernaz, E., 1990. Scientific Basis for Nuclear Waste Management, 176, Material Research Society.
4. ASTM, 1994. Standard Test Methods for Determining Chemical Durability of Nuclear Waste Glasses: The Product Consistency Test (PCT). ASTM C1285, American Society for Testing and Materials International, Philadelphia, PA.
5. Bacon, D.H., White, M.D., McGrail, B.P., 2004. Subsurface Transport Over Reactive Multiphases (STORM): A Parallel, Coupled, Nonisothermal Multiphase Flow, Reactive Transport, and Porous Medium Alteration Simulator, Version 3.0, PNNL-14783, Pacific Northwest National Laboratory, Richland, WA.
6. Barkatt A., Gibson B.C., Macedo P.B., Montrose C.J., Sousanpour W., Barkatt A., Boroomand M.-A., Rogers V., and Penafiel M. Mechanisms of defense waste glass dissolution. Nucl. Technol. 73 (1986) 140-164
7. Berger G., Cadore E., Schott J., and Dove P.M. Dissolution rate of quartz in lead and sodium electrolyte solutions between 25 and 300 °C: effect of the nature of surface complexes and reaction affinity. Geochim. Cosmochim. Acta 58 (1994) 541-551
8. Bourcier W.L. Overview of chemical modeling of nuclear waste glass dissolution. Mater. Res. Symp. Proc. 212 (1991) 3-17
9. Bourcier W.L. Waste glass corrosion modeling: comparison with experimental results. Mater. Res. Symp. Proc. 333 (1994) 69-81
10. Bourcier, W.L., Peiffer, D.W., Knauss, K.G., McKeegan, K.D., Smith, D.K., 1990. Scientific Basis for Nuclear Waste Management, 176. Materials Research Society.
11. Brady P.V., and House W.A. Surface-controlled dissolution and growth of minerals. In: Brady P.V. (Ed). Physics and Chemistry of Mineral Surfaces (1996), CRC Press, New York, NY 249-256
12. Brunauer S., Emmett P.H., and Teller E. Adsorption of Gases in Multimolecular Layers. J. Am. Chem. Soc. 60 (1938) 309-319
13. Bunker B.C., Tallant D.R., Headley T.J., Turner G.L., and Kirkpatrick R.J. The structure of leached sodium borosilicate glass. Phys. Chem. Glasses 29 (1988) 106-120
14. Casey, W.H., Bunker, B.C., 1990. Leaching of mineral and glass surfaces during dissolution. In: Hochella Jr., M.F., White, A.F. (Eds), Mineral-Water Interface Geochemistry. Reviews in Mineralogy, vol. 23, pp. 397-426.
15. Casey W.H., and Westrich H.R. Control of dissolution rates of orthosilicate minerals by divalent metal oxygen bonds. Nature 355 6356 (1992) 157-159
16. Chou L., and Wollast R. Study of the weathering of albite at room temperature and pressure with a fluidized bed reactor. Geochim. Cosmochim. Acta 48 (1984) 2205-2217
17. Devidal J.L., Schott J., and Dandurand J.L. An experimental study of kaolinite dissolution and precipitation kinetics as a function of chemical affinity and solution composition at 150 °C, 40 bars, and pH 2, 6.8, and 7.8. Geochim. Cosmochim. Acta 61 (1997) 5165-5186
18. DOE, 1994a. High-level Borosilicate Waste Glass: A Compendium of Corrosion Characteristics, vol. 1, DOE-EM-0177, US Department of Energy Office of Waste Management, Springfield, VA.
19. DOE, 1994b. High-Level Waste Borosilicate Glass: A Compendium of Corrosion Characteristics, vol. 2, DOE-EM-0177, US Department of Energy Office of Waste Management, Springfield, VA.
20. Dove P.M. The dissolution kinetics of amorphous silica into sodium chloride solutions: effects of temperature and ionic strength. Am. J. Sci. 294 (1994) 665-712
21. Eyring H. The activated complex in chemical reactions. J. Chem. Phys. 3 (1935) 107-114
22. Freeman H., and Hill H.D.W. Fourier transform study of NMR spin-lattice relaxation by "progressive saturation". J. Chem. Phys. 54 (1971) 3367
23. Gin S., Jollivet P., Mestre J.P., Jullien M., and Pozo C. French SON 68 nuclear glass alteration mechanisms on contact with clay media. Appl. Geochem. 16 (2001) 861-881
24. Grambow B. A general rate equation for nuclear waste glass corrosion. Mater. Res. Symp. Proc. 44 (1985) 15-27
25. Grambow B. Nuclear waste glasses - how durable. Elements 2 (2006) 357-364
26. Grambow B., and Müller R. First-order dissolution rate law and the role of surface layers in glass performance assessment. J. Nucl. Mater. 298 (2001) 112-124
27. Hamilton J.P., Brantley S.L., Pantano C.G., Criscenti L.J., and Kubicki J.D. Dissolution of nepheline, jadeite, and albite glasses: toward better models for aluminosilicate dissolution. Geochim. Cosmochim. Acta 65 (2001) 3683-3702
28. Hench L.L., Clark D.E., and Harker A.B. Nuclear waste solids. J. Mater. Sci. 21 (1986) 1457-1478
29. Holdren G.R., and Speyer P.M. Reaction rate-surface area relationships during the early stages of weathering. II. Data on eight additional feldspars. Geochim. Cosmochim. Acta 51 (1987) 2311-2318
30. Icenhower J.P., and Dove P.M. The dissolution kinetics of amorphous silica in sodium chloride solutions: effects of temperature and ionic strength. Geochim. Cosmochim. Acta 64 (2000) 4193-4203
31. Icenhower, J.P., Samson, S., Luttge, A., McGrail, B.P., 2004. Towards a consistent rate law: glass corrosion kinetics near saturation. In: Giere, R., Stille, P. (Eds.), Energy, Waste, and the Environment: A Geochemical Perspective. Special Publication 236. Geological Society of London, pp. 579-594.
32. Icenhower J.P., Strachan D.M., McGrail B.P., Scheele R.D., Rodriguez E.A., Steele J.L., and Legore V.L. Dissolution kinetics of pyrochlore ceramics for the disposition of plutonium. Am. Mineral. 91 (2006) 39-53
33. Jantzen C.M. Nuclear waste glass durability: I, predicting environmental response from thermodynamic (pourbaix) diagrams. J. Am. Ceramic Soc. 75 (1992) 2433-2448
34. Jantzen C.M., and Plodinec M.J. Thermodynamic model of natural, medieval, and nuclear waste glass durability. J. Non-Cryst. Solids 67 (1984) 207-223
35. Jegou C., Gin S., and Larche F. Alteration kinetics of a simplified nuclear glass in an aqueous medium: effects of solution chemistry and of protective gel properties on diminishing the alteration rate. J. Nucl. Mater. 280 (2000) 216-229
36. Lasaga, A.C., 1981. Transition state theory. In: Lasaga, A.C., Kirkpatrick, R.J. (Eds), Kinetics of Geochemical Processes. Reviews in Mineralogy, vol. 8, pp. 135-168.
37. Lasaga A.C. Fundamental approaches in describing mineral dissolution and precipitation rates. In: White A.F., and Brantley S.L. (Eds). Chemical Weathering Rates of Silicate Minerals vol. 31 (1995), Mineralogical Society of America, Washington, DC 3-86
38. Mann, F.M., Puigh, R.J., Finfrock, S., Freeman, E.J., Khaleel, R., Bacon, D.H., Bergeron, M.P., McGrail, B.P., Wurstner, S.K., Burgard, K., Root, W.R., LaMont, P.E., 2001. Hanford Immobilized Low-Activity Tank Waste Performance Assessment: 2001 Version., DOE/ORP-2000-24, Rev.0, US Department of Energy, Richland, Washington.
39. McGrail B.P., Lindenmeier C.W., Martin P.F., and Gee G.W. The pressurized unsaturated flow (PUF) test: a new method for engineered-barrier materials evaluation. In: Jain V., and Peeler D.K. (Eds). Environmental Issues and Waste Management Technologies in the Ceramic and Nuclear Industries II vol. 72 (1996), The American Ceramic Society, Westerville, OH 317-329
40. McGrail B.P., Ebert W.L., Bakel A.J., and Peeler D.K. Measurement of kinetic rate law parameters on a Na-Ca-Al borosilicate glass for low-activity waste. J. Nucl. Mater. 249 (1997) 175-189
41. McGrail B.P., Lindenmeier C.W., and Martin P.F. Characterization of pore structure and hydraulic property alteration in pressurized unsaturated flow tests. In: Wronkiewicz D.J., and Lee J.H. (Eds). Material Research Symposium Proceedings: Scientific Basis for Nuclear Waste Management vol. 556 (1999), Material Research Society 421-428
42. McGrail, B.P., Bacon, D.H., Ebert, W.L., Saripalli, K.P., 2000a. A Strategy to Conduct an Analysis of the Long-Term Performance of Low-Activity Waste Glass in a Shallow Subsurface Disposal System at Hanford. PNNL-11834 Rev.1, Pacific Northwest National Laboratory, Richland, WA.
43. McGrail, B.P., Icenhower, J.P., Martin, P.F., Rector, D.R., Schaef, H.T., Rodriguez, E.A., Steele, J.L., 2000b. Low-Activity Waste Glass Studies: FY2000 Summary Report, PNNL-13381, Pacific Northwest National Laboratory, Richland, WA.
44. McGrail B.P., Bacon D.H., Icenhower J.P., Mann F.M., Puigh R.J., Schaef H.T., and Mattigod S.V. Near-field performance assessment for a low-activity waste glass disposal system: laboratory testing to modeling results. J. Nucl. Mater. 298 (2001) 95-111
45. 2O. J. Non-Cryst. Solids 296 (2001) 10-26
46. McGrail, B.P., Bacon, D.H., Serne, R.J., Pierce, E.M., 2003. A Strategy to Assess Performance of Selected Low-Activity Waste Forms in an Integrated Disposal Facility, PNNL-14362, Pacific Northwest National Laboratory, Richland, WA.
47. Muller, I.S., Buechele, A.C., Pegg, I.L., 2001. Final Report: Glass Formulation and Testing with RPP-WTP-LAW Simulants, VSL-01R3560-2, Vitreous State Laboratory, Catholic University of America, Washington, DC.
48. Oelkers E.H., Schott J., and Devidal J.L. The effect of aluminum, pH, and chemical affinity on the rates of aluminosilicate dissolution reactions. Geochim. Cosmochim. Acta 58 (1994) 2011-2024
49. Oelkers E.H., Schott J., and Devidal J.L. On the interpretation of closed system mineral dissolution experiments: Comment on "Mechanism of kaolinite dissolution at room temperature and pressure Part II: Kinetic study" by Huertas et al. (1999). Geochim. Cosmochim. Acta 65 (2001) 4429-4432
50. Paul A. Chemical durability of glasses; a thermodynamic approach. J. Mater. Sci. 12 (1977) 2246-2268
51. Paul A. Chemistry of Glasses (1982), Chapman and Hall
52. Pierce, E.M., McGrail, B.P., Rodriguez, E.A., Schaef, H.T., Saripalli, K.P., Serne, R.J., Krupka, K.M., Martin, P.F., Baum, S.R., Geiszler, K.N., Reed, L.R., Shaw, W.J., 2004. Waste Form Release Data Package for the 2005 Integrated Disposal Facility Performance Assessment, PNNL-14805, Pacific Northwest National Laboratory, Richland, WA.
53. 2(cr) dissolution kinetics: effects of solution saturation state and pH.J. Nucl. Mater. 345 (2005) 206-218
54. Pierce E.M., McGrail B.P., Valenta M.M., and Strachan D.M. The accelerated weathering of a radioactive low-activity waste glass under hydraulically unsaturated conditions: experimental results from a pressurized unsaturated flow (PUF) test. Nucl. Technol. 155 (2006) 133-148
55. Pierce E.M., McGrail B.P., Marra J., Martin P.F., Arey B.W., and Geiszler K.N. Accelerated weathering of a high-level and pu-bearing lanthanide borosilicate waste glass in a can-in-canister configuration. Appl. Geochem. 22 (2007) 1841-1859
56. Pierce E.M., Richards E.L., Davis A.M., Reed L.R., and Rodriguez E.A. Aluminoborosilicate waste glass dissolution under alkaline conditions at 40 °C: implications for a chemical affinity-based rate equation. Environ. Chem. 5 (2008) 73-85
57. 4) Join. Geochim. Cosmochim. Acta.
58. Pierce, E.M., McGrail, B.P., Cordova, E.A., submitted for publication-c. An experimental study of the dissolution rates of simulated aluminoborosilicate waste glasses under dilute and near Si saturated conditions. Appl. Geochem.
59. Plodinec M.J., Jantzen C.M., and Wicks G.G. Stability of radioactive waste glasses assessed from hydration thermodynamics. In: McVay G.L. (Ed). Scientific Basis for Nuclear Waste Management VII vol. 26 (1984), Elsevier Science Publishing Co
60. Puigh, R.J., 1999. Disposal Facility Data for the Hanford Immobilized Low-Activity Tank Waste, HNF-4950, Rev. 1, Flour Federal Services, Richland, Washington.
61. Renders P.J.N., Gammons C.H., and Barnes H.L. Precipitation and dissolution rate constants for cristobalite from 150 to 300 °C. Geochim. Cosmochim. Acta 59 (1995) 77-85
62. Rimstidt J.D., and Dove P.M. Mineral solution reaction-rates in a mixed flow reactor - wollastonite hydrolysis. Geochim. Cosmochim. Acta 50 (1986) 2509-2516
63. Scheetz, B.E., Freeborn, W.P., Smith, D.K., Anderson, C., Zolensky, M., 1985. The role of boron in monitoring the leaching of borosilicate glass waste forms. In: Material Research Society Symposium Proceedings, vol. 44. Materials Research Society, pp. 129-134.
64. Small, J.S., Humphrey, P.N., Johnstone, T.L., Plant, R., Randall, M.G., Trivedi, D.P., 2000. Results of an aqueous source term model for a radiological risk assessment of the Drigg LLW Site, UK. In: Smith, R.W., Shoesmith, D.W. (Eds.), Scientific Basis for Nuclear Waste Management XXIII, vol. 608. Materials Research Society, pp. 129-134.
65. Strachan D.M., and Croak T.L. Compositional effects on long-term dissolution of borosilicate glass. J. Non-Cryst. Solids 272 (2000) 22-33
66. Strachan, D.M., Bourcier, W.L., McGrail, B.P., 1993. Toward a consistent model for glass dissolution. Radioactive Waste Management and Environmental Restoration 000(2), pp. 1-17.
67. Techer I., Advocat T., Lancelot J., and Liotard J.-M. Basaltic glass: alteration mechanisms and analogy with nuclear waste glasses. J. Nucl. Mater. 282 (2000) 40-46
68. Vernaz E., and Dussossoy J.L. Current state of knowledge of nuclear waste glass corrosion mechanisms: the case of R7T7 glass. Appl. Geochem. 1 (1992) 13-22
69. Vernaz E., Gin S., Jegou C., and Ribet I. Present understanding of R7T7 glass alteration kinetics and their impact on long-term behavior modeling. J. Nucl. Mater. 298 (2001) 27-36
70. Vienna, J.D., 2005. Preliminary ILAW Formulation Algorithm Description, 24590-LAW-RPT-RT-04-0003, Rev.0, Bechtel National, Richland, WA.
71. 2O. Am. Mineral. 91 (2006) 143-158
72. Werme L.O., Bjorner I.K., Bart G., Lutze W., Ewing R.C., and Magrabi C. Chemical corrosion of highly radioactive borosilicate nuclear waste glass under simulated repository conditions. J. Mater. Res. 5 (1990) 1130-1146
73. White, A.F., Brantley, S.L., 1995. Chemical Weathering Rates in Silicates. Mineralogical Society of America.
74. Wolery,T.J., 1992. EQ3NR, A Computer Program for Geochemical Aqueous Speciation-Solubility Calculations: Theoretical Manual, User's Guide, and Related Documentation (Version 7.0), UCRL-MA-110662 PT III, Lawrence Livermore National Laboratory, Livermore, CA.
75. Wolff-Boenisch D., Gislason S.R., Oelkers E.H., and Putnis C. The dissolution rates of natural glasses as a function of their composition at pH 4 and 10.6, and temperatures from 25 to 74 °C. Geochim. Cosmochim. Acta 68 (2004) 4843-4858