Vitrification of High-level Radioactive Waste in a Small-scale Joule-heated Ceramic Melter

Vitrification of High-level Radioactive Waste in a Small-scale Joule-heated Ceramic Melter
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Release: 1981
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Vitrification is the reference process for the immobilization of radioactive waste from the production of defense materials at the Savannah River Plant (SRP). Since 1979, a small vitrification facility (1 lb/h) has been operated at the Savannah River Laboratory using actual SRP waste. In previous studies, dried waste was fed to this smaller melter. This report discusses direct feeding of actual liquid-waste slurries to the small melter. These liquid-feeding tests demonstrated that addition of premelted glass frit to the waste slurry reduces the amount of material volatilized. Results of these tests are in accord with results of large-scale tests with actual waste.

Experience with Waste Vitrification Systems at Battelle-Northwest

Experience with Waste Vitrification Systems at Battelle-Northwest
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Release: 1975
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Three types of melters; in-can, continuous metallic, and joule-heated ceramic are being developed on an engineering scale for conversion of simulated high-level radioactive waste to a glass form. Work with each of the three melters has progressed for over a year, and ton quantities of glass have been produced. The operation and performance of these systems are described. (auth).

Experimental Joule-heated Ceramic Melter for Converting Radioactive Waste to Glass

Experimental Joule-heated Ceramic Melter for Converting Radioactive Waste to Glass
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Release: 1978
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A small electric melter was developed to implement studies for converting radioactive waste to glass at the Savannah River Laboratory (SRL). The ceramic-lined, joule-heated melter has been in operation for ten months. During this period, simulated, high-level-waste, calcined materials and frit were processed at rates of 2 to 15 g/min. The melt chamber is 7.6-cm wide, 22.9-cm long and 7.6-cm deep. The total power consumption is 3.5 KVA when the glass processing temperature is 1150°C. A similar unit will be in operation in FY-1979 in the SRL high-level cells.

Design and Operation of Small-scale Glass Melters for Immobilizing Radioactive Waste

Design and Operation of Small-scale Glass Melters for Immobilizing Radioactive Waste
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Release: 1980
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A small-scale (3-kg), joule-heated, continuous melter has been designed to study vitrification of Savannah River Plant radioactive waste. The first melter built has been in nonradioactive service for nearly three years. This melter had Inconel 690 electrodes and uses Monofrax K-3 for the contact refractory. Several problems seem in this melter have had an impact on the design of a full-scale system. Problems include uncontrolled electric currents passing through the throat, and formation of a slag layer at the bottom of the melter. The performance of a similar melter in a low-maintenance, radioactive environment is also described. Problems such as halide refluxing, and hot streaking, first observed in this melter, are also discussed.

Characterization of Radioactive Waste Melter Feed Vitrified By Microwave Energy

Characterization of Radioactive Waste Melter Feed Vitrified By Microwave Energy
Author: Carol M. Jantzen
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Total Pages: 9
Release: 1992
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ISBN:

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Liquid high-level nuclear waste will be immobilized at the Savannah River Site (SRS) by vitrification in borosilicate glass. The glass win be processed in the Defense Waste Processing Facility (DWPF) and poured into stainless steel canisters for eventual disposal in a geologic repository. Vitrification of melter feed samples is necessary for DWPF process and product control. Microwave fusion of melter feed at approximately 12OO deg C for 10 minutes has been shown to yield homogeneous glasses comparable to those melted in a conventional furnace for 4 hours. Microwave fusion at lower temperatures for longer times was found to crystallize NiFe2O4 spinel. The use of higher temperatures was determined to cause significant volatilization and recrystallization of the glass. Redox measurements indicated that microwave vitrification of melter slurries may also yield more representative measures of glass Fe2+/Sigma Fe ratio of the glass which is important to melter processing of the glass.

High-temperature Vitrification of Low-level Radioactive and Hazardous Wastes

High-temperature Vitrification of Low-level Radioactive and Hazardous Wastes
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Total Pages: 10
Release: 1995
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The US Department of Energy (DOE) weapons complex has numerous radioactive waste streams which cannot be easily treated with joule-heated vitrification systems. However, it appears these streams could be treated With certain robust, high-temperature, melter technologies. These technologies are based on the use of plasma torch, graphite arc, and induction heating sources. The Savannah River Technology Center (SRTC), with financial support from the Department of Energy, Office of Technology Development (OTD) and in conjunction with the sites within the DOE weapons complex, has been investigating high-temperature vitrification technologies for several years. This program has been a cooperative effort between a number of nearby Universities, specific sites within the DOE complex, commercial equipment suppliers and the All-Russian Research Institute of Chemical Technology. These robust vitrification systems appear to have advantages for the waste streams containing inorganic materials in combination with significant quantities of metals, organics, salts, or high temperature materials. Several high-temperature technologies were selected and will be evaluated and employed to develop supporting technology. A general overview of the SRTC ''High-Temperature Program'' will be provided.