Thermodynamic stability of waste glasses compared to leaching behaviour

The thermodynamic stability of products obtained from the high-temperature treatment of municipal solid wastes and their associated residues (bottom ash, fly ash, filter cake, optional additives) can be estimated by calculation of their free energy of hydration ΔGhydr by a polyhedral approach. This approach has been applied on a series of 23 samples originating from high-temperature treatment processes operated under a range of conditions, and 3 thoroughly characterised standards. For vitreous or vitrocrystalline samples, it is demonstrated that Si and Ca contents clearly control their thermodynamic stability, and that the type of incineration process plays only a minor role. Silicon directly influences the durability of the samples, while Ca governs the pH during corrosion, which in turn affects the thermodynamic stability. It is also shown that there is a tight inverse relationship between the calculated thermodynamic stability of the samples and their rates of dissolution under aggressive conditions of corrosion. Attempts to compare the results to the large literature database of results obtained from nuclear high-level waste glasses, their proxies and other analogs (ancient and commercial glasses) are limited by sample preparation constraints. It is however concluded that the calculated thermodynamic stability of these “waste glasses” offers a valid estimate for their relative quality and, in turn, for their durability.

[1]  B. Grambow,et al.  Remaining Uncertainties in Predicting Long-Term Performance of Nuclear Waste Glass From Experiments , 1993 .

[2]  H. Scholze Chemical durability of glasses , 1982 .

[3]  J. Thomassin,et al.  Archaeological glasses as modelling of the behavior of buried nuclear waste glass , 1992 .

[4]  S. Gíslason,et al.  The mechanism, rates and consequences of basaltic glass dissolution: I. An experimental study of the dissolution rates of basaltic glass as a function of aqueous Al, Si and oxalic acid concentration at 25°C and pH = 3 and 11 , 2001 .

[5]  Bernd Grambow,et al.  First-order dissolution rate law and the role of surface layers in glass performance assessment , 2001 .

[6]  K. Shimizu,et al.  Examination and Testing of an Active Glass Sample Produced by Cogema , 1994 .

[7]  Werner Lutze,et al.  Scientific basis for nuclear waste management , 1979 .

[8]  A. Paccagnella,et al.  Hydrated-layer formation during dissolution of complex silicate glasses and minerals , 1990 .

[9]  A. Paul Chemical durability of glasses; a thermodynamic approach , 1977 .

[10]  Amala Paul Chemistry of glasses , 1982 .

[11]  K. Gillies,et al.  Decay of medieval stained glass at York, Canterbury and Carlisle. II: Relationship between the composition of the glass, its durability and the weathering products , 1988 .

[12]  C. Jantzen Effects of Eh (oxidation potential) on borosilicate waste glass durability , 1984 .

[13]  C. Jantzen,et al.  Stability of Radioactive Waste Glasses Assessed from Hydration Thermodynamics , 1983 .

[14]  C. Jantzen,et al.  High level radioactive waste glass production and product description , 1993 .

[15]  J. Crovisier,et al.  Dissolution of subglacial volcanic glasses from Iceland: laboratory study and modelling , 1992 .

[16]  C. Jantzen,et al.  Thermodynamic model of natural, medieval and nuclear waste glass durability , 1984 .

[17]  R. Newton,et al.  The durability of glass: a review , 1985 .

[18]  J. L. Dussossoy,et al.  Current state of knowledge of nuclear waste glass corrosion mechanisms: the case of R7T7 glass , 1992 .

[19]  P. Colombel Etude du comportement à long terme de vitrifiats de REFIOM , 1996 .

[20]  J. C. Cunnane,et al.  High-level waste borosilicate glass: A compendium of corrosion characteristics. Volume 3 , 1994 .

[21]  J. Crovisier,et al.  Dissolution of basaltic glass in seawater: Mechanism and rate , 1987 .

[22]  Eric H. Oelkers,et al.  General kinetic description of multioxide silicate mineral and glass dissolution , 2001 .

[23]  J. Crovisier,et al.  Early phyllosilicates formed by alteration of R7T7 glass in water at 250°C , 1992 .

[24]  B. Grambow,et al.  A General Rate Equation for Nuclear Waste Glass Corrosion , 1984 .

[25]  P. Jollivet,et al.  Estimating the alteration kinetics of the French vitrified high-level waste package in a geologic repository , 1998 .

[26]  G. Malow The Mechanisms for Hydrothermal Leaching of Nuclear Waste Glasses: Properties and Evaluation of Surface Layers , 1981 .

[27]  J. Crovisier,et al.  A new method for studying leached glasses: Analytical electron microscopy on ultramicrotomic thin sections , 1986 .

[28]  B. Grambow,et al.  Leach Testing of Waste Glasses Under Near-Saturation Conditions , 1983 .

[29]  W. Ebert,et al.  Laboratory Testing of Waste Glass Aqueous Corrosion; Effects of Experimental Parameters , 1993 .

[30]  J. Thomassin,et al.  Etude des premiers stades de l'interaction eau-verre basaltique : données de la spectrométrie de photoélectrons (XPS) et de la microscopie électronique à balayage , 1979 .

[31]  Jérôme Sterpenich Altération des vitraux médiévaux. Contribution à l'étude du comportement à long terme des verres de confinement , 1998 .

[32]  Iu. P. Raizer Gas Discharge Physics , 1991 .

[33]  R. A. Van Konynenburg,et al.  Scientific basis for nuclear waste management XVII , 1994 .