An Evaluation of Vitrification Technology

An Evaluation of Vitrification Technology
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Total Pages: 12
Release: 1994
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Argonne National Laboratory-East (ANL-E) is evaluating the feasibility of using vitrification to treat mixed wastes. This program is in the process of identifying glass compositions that can be produced from mixed wastes and additives, with an emphasis on maximizing the waste loading in the glass, and the overall waste volume reduction. Preliminary crucible glass studies with surrogate mixed waste streams have produced a glass composition that could be produced in commercially available melters. This same glass composition, spiked with Resource Conservation Recovery Act (RCRA) metals, pass the Toxic Characteristic Leaching Procedure (TCLP) test. Thus, the final waste form is a low-level radioactive waste. Additional crucible melts with actual mixed waste streams are in progress and will define a compositional envelope of acceptable glasses that will eventually be produced during full-scale melter operations. Evaluations of the likely off-gases from vitrification indicate that the primary off-gases produced during vitrification will include compounds of SO(subscript x), NO(subscript x) and CO2. These compounds are routinely treated in the off-gas portion of vitrification systems. The composition of the melter feed can be adjusted to control some of the off-gases produced, if necessary. The economics suggest that annual cost savings resulting from volume reduction and conversion of mixed waste to low-level waste may be substantial.

Vitrification of Low-level Radioactive Mixed Waste at Argonne National Laboratory

Vitrification of Low-level Radioactive Mixed Waste at Argonne National Laboratory
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Total Pages: 14
Release: 1995
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Argonne National Laboratory-East (ANL-E) is proceeding with plans to use vitrification to treat low-level radioactive mixed wastes (LLMW) generated on-site. The objective is to install a full-scale vitrification system at ANL-E capable of processing the entire annual generation of selected LLMW streams. Crucible glass studies with actual mixed waste streams have produced sodium borosilicate glasses under conditions achievable in commercially available melters. These same glass compositions, spiked with toxic metals above the expected levels in actual wastes, pass the Toxicity Characteristic Leaching Procedure (TCLP) test. Earlier evaluations of the likely off-gases that will result from vitrification indicated that the primary off-gases will include compounds of SO(subscript x), NO(subscript x), and CO2. These evaluations are being experimentally confirmed with a mass spectrometer analysis of the gases evolved from samples of the ANL-E wastes. The composition of the melter feed can be adjusted to minimize volatilization of some components, if necessary. The full-scale melter will be designed to handle the annual generation of at least three LLMW waste streams: evaporator concentrator bottoms sludge (ECB), storage tank sludge (STS), and HEPA filter media. Each waste stream is mixed waste by virtue of its failure to pass the TCLP test with respect to toxic metal leaching. Additional LLMW streams under consideration for vitrification include historical mixed waste glass from past operations and spent abrasive from a planned decontamination facility.

Oak Ridge National Laboratory West End Treatment Facility Simulated Sludge Vitrification Demonstration, Revision 1

Oak Ridge National Laboratory West End Treatment Facility Simulated Sludge Vitrification Demonstration, Revision 1
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Total Pages: 26
Release: 1994
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Technologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to convert hazardous and mixed wastes to a form suitable for permanent disposal. Vitrification, which has been declared the Best Demonstrated Available Technology for high-level radioactive waste disposal by the EPA, is capable of producing a highly durable wasteform that minimizes disposal volumes through organic destruction, moisture evaporation, and porosity reduction. However, this technology must be demonstrated over a range of waste characteristics, including compositions, chemistries, moistures, and physical characteristics to ensure that it is suitable for hazardous and mixed waste treatment. These wastes are typically wastewater treatment sludges that are categorized as listed wastes due to the process origin or organic solvent content, and usually contain only small amounts of hazardous constituents. The Oak Ridge National Laboratory's (ORNL) West End Treatment Facility's (WETF) sludge is considered on of these representative wastes. The WETF is a liquid waste processing plant that generates sludge from the biodenitrification and precipitation processes. An alternative wasteform is needed since the waste is currently stored in epoxy coated carbon steel tanks, which have a limited life. Since this waste has characteristics that make it suitable for vitrification with a high likelihood of success, it was identified as a suitable candidate by the Mixed Waste Integrated Program (MWIP) for testing at CU. The areas of special interest with this sludge are (1) minimum nitrates, (2) organic destruction, and (3) waste water treatment sludges containing little or no filter aid.

Vitrification of M-Area Mixed (Hazardous and Radioactive) F006 Wastes

Vitrification of M-Area Mixed (Hazardous and Radioactive) F006 Wastes
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Total Pages: 5
Release: 2001
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Technologies are being developed by the US Department of Energy's (DOE) Nuclear Facility sites to convert low-level and mixed (hazardous and radioactive) wastes to a solid stabilized waste form for permanent disposal. One of the alternative technologies is vitrification into a borosilicate glass waste form. The Environmental Protection Agency (EPA) has declared vitrification the Best Demonstrated Available Technology (BDAT) for high-level radioactive mixed waste and produced a Handbook of Vitrification Technologies for Treatment of Hazardous and Radioactive Waste. The DOE Office of Technology Development (OTD) has taken the position that mixed waste needs to be stabilized to the highest level reasonably possible to ensure that the resulting waste forms will meet both current and future regulatory specifications. Stabilization of low level and hazardous wastes in glass are in accord with the 1988 Savannah River Technology Center (SRTC), then the Savannah River Laboratory (SRL), Professional Planning Committee (PPC) recommendation that high nitrate containing (low-level) wastes be incorporated into a low temperature glass (via a sol-gel technology). The investigation into this new technology was considered timely because of the potential for large waste volume reduction compared to solidification into cement.