Waste glasses

Glass is a product of the super-cooUng of a melted hquid mixture consisting primarily of sand (silicon dioxide) and soda ash (sodium carbonate) to a rigid condition, in which the super cooled material does not crystaUize and retains the organization and internal structure of the melted hquid. When waste glass is crushed to sand size particles, similar to those of natural sand, it exhibits properties of an aggregate material [207-214]. 

In 1994 approximately 9.2 million metric tons (10.2 milhon tons) of postconsumer glass was discarded in the municipal sohd waste stream in the United States. Approximately 8.1 milhon metric tons (8.9 milhon tons) or 80% of this waste glass was container glass [210-213]. 

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Waste glass Waste glass within household refuse No utilization in household refuse If segregated, recycled... 

The slow rate of dissolution of, or leaching from, durable glasses has led to proposals for the vitrification of nuclear waste. Glasses based on the sodium borosilicate system appear to be favoured because of their ability to dissolve the waste, combined with good chemical durability. Intensive development has taken place over recent ycars and a regular journal is devoted to this topic . 

Peters, R.D. Diamond, H. "Actinide Leaching from Waste Glass Air-Equilibrated versus Deaerated Conditions", Report PNL-3971, Battelle Pacific Northwest Laboratory, 1981. 

A novel process to produce chlorine-free fuel gas and char from waste PVC and waste glass... 

Authors have proposed a novel process not to dispose to landfill sites both waste PVC and waste glass but to utilize them to produce fuel and neutralize each other at the same moment. It has been successfully demonstrated that hydrogen chloride produced during flash pyrolysis of PVC was completely neutralized by the fixed glass bed and thus chlorine-lree fuel was produced [1-2]. To carry forward our proposed process we need to know the kinetics of the neutralization process. Also we have to solve the problem of formation of metal chlorides in the product char during pyrolysis of PVC, which is a critical issue for its thermal utilization. Consequently, in the present study the evaluations of neutralization kinetics of glass cullets and the decomposition of CaCl2 in char by steam were conducted. 

The Commission is working on establishing end-of-waste criteria for a number of specific recyclable materials including metal scrap of copper, aluminum and iron, waste paper, waste glass, compost, and plastics. Based on the results of two frontrunner studies, ferrous scrap and aluminum scrap in 2010, the first... 

Jantzen, C.M. and Plodinec, M.J. (1984). Thermodynamic model of natural, Medieval and nuclear waste glass durability. Journal of Non-Crystalline Solids 67 207-223. 

Typically cullet, recycled or waste glass (5%-40%), is added along with the principle raw materials (mostly Si02). The mixture is thoroughly mixed and then added to a furnace where the mixture is heated to near 1500°C to form a viscous, syruplike liquid. The size and nature... 

Gamma-irradiation has been used to investigate effects on chemical durability of waste glasses (Lutze 1988) and to assess the effect on corrosion and defect formation in waste ceramics (Vlasov et al. 1987 Kulikov et al. 2001). Irradiation with Y-rays does not produce atomic displacements, but rather causes excitations and point defects and leads to formation of ion radicals. Therefore, this method may serve as a simulation for p-Y-radiation of FPs in the waste forms. 

Most leach rate measurements of both matrix elements and radionuclides were performed at 90 °C using MCC-1 or PCT tests. According to these tests, leach rates range from 10 1 to 10g m 2 d (Lutze 1988). For example, the mass and elemental leach rates (in g-m 2-d ) for the PNL 76-68 glass containing 33 wt% waste oxides were determined at mass - 0.42, Ca - 0.068, Cs - 1.03, Mo - 1.40, Na - 1.32, Sr - 0.075, B - 1.12, and Si - 0.73. These values are typical for borosilicate waste glass as measured by the MCC-1 procedure (90 °C, 28 d). Leach rates of Fe-group elements and ACTs under the same test conditions are considerably lower (10-3 and 10 4g-m 2-d , respectively). 

ASTM 1994. Standard Test Methods for Determining Chemical Durability of Nuclear Waste Glasses The Product Consistency Test (PCT). Standard Cl285-94. ASTM, Philadelphia. 

DeNatale, J. F. Howjtt, D. G. 1985. The gamma-irradiation of nuclear waste glasses. Radiation Effects, 91, 89-96. 

Jain, V. Barnes, S. M. 1997. Radioactive waste glass production at the WVDP. In Waste Management 97 Conference. Laser Options, Inc., Tucson, CD-ROM. 

Buck, E. C. Bates, J. K. 1999. Microanalysis of colloids and suspended particles from nuclear waste glass alteration. Applied Geochemistry, 14, 635-653. 

Abdelouas, A., Crovisier, J. L., Lutze, W., Fritz, B., Mosser, A. Muller R. 1994. Formation of hydrotalcite-like compounds during R7T7 nuclear waste glass and basaltic glass alteration. Clays and Clay Minerals, 42, 526-533. 

Byers, C. D., Ewing, R. C. Jercinovic, M. J. 1987a. Experimental alteration of basalt glass applied to the alteration of nuclear waste glass. Advances in Ceramics, 20, 733 -744. 

Curti, E., Crovisier, J.-L., Karpoff, A.-M. Munier, I. Long-term glass alteration of two simulated nuclear waste glasses (MW and SON68) kinetics and geochemical results, (in preparation). 

Gong, W. L., Wang, L. M., Ewing, R. C., Vernaz, E., Bates, J. K. Ebert, W. L. 1998. Analytical electron microscopy study of surface layers formed on the French SON68 nuclear waste glass during vapor hydration at 200°C. Journal of Nuclear Materials, 254, 249-265. 

Malow, G. Ewing, R. C. 1981. Nuclear waste glasses and volcanic glasses a comparison of their stabilities. In Moore, J. G. (ed) Scientific Basis for Nuclear Waste Management III. Plenum Publishing Corp., New York, 315-322. 

Liotard, J.-M. 2000. Basaltic glass alteration mechanisms and analogy with nuclear waste glasses. Journal of Nuclear Materials, 282, 40-46. 

The unique setting of the Werra-Fulda district allows not only the study of basalt alteration, but also the ability to trace basalt-derived elements within the salt. The study site is thus, on one hand, a natural analogue for the long-term corrosion expected for nuclear waste glass in... 

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