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.
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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.
| Author | : |
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| Total Pages | : 104 |
| Release | : 1992 |
| Genre | : Glass furnaces |
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| Author | : National Research Council |
| Publisher | : National Academies Press |
| Total Pages | : 172 |
| Release | : 1997-03-02 |
| Genre | : Science |
| ISBN | : 0309056829 |
| Author | : |
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| Total Pages | : 5 |
| Release | : 2002 |
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Hanford tank waste consists of about 190 million curies in 54 million gallons of highly radioactive and mixed hazardous waste stored in underground storage tanks at the Hanford Site in Washington State. The tank waste includes solids (sludge), liquids (supernatant), and salt cake (dried salts that dissolve in water to form supernatant). The tank waste will be remediated through treatment and immobilization to protect the environment and meet regulatory requirements. The U.S. Department of Energy's (DOE's) preferred alternative to remediate the Hanford tank waste is to pretreat the waste by separating it into low-activity waste (LAW) and high-level waste (HLW), followed by immobilization of the LAW for on-site disposal and immobilization of the HLW for ultimate disposal in a national repository. This paper describes the crucible-scale vitrification and associated wasteform product tests in support of the WTP at Hanford. The two different LAW glasses produced in this study were from pretreated Envelope A (Tank 241-AN-103) and Envelope C (Tank 241-AN-102) waste. The HLW glass was produced from Tank C-106 HLW sludge and the HLW radionuclide products separated from Hanford Site tank samples AN-103, AN-102 and AZ-102. Pretreatment of these three supernates consisted of characterization, strontium and transuranics removal by precipitation and filtration, and final Cs-137 and Tc-99 removal by ion exchange (IX). The glasses were produced from formulations supplied by Vitreous State Laboratory of the Catholic University of America (CUA). Formulations were based on previous surrogate testing and the actual characterization data from the radioactive feed streams. Crucible-scale vitrifications were performed in platinum/gold crucibles in a custom-designed furnace fit with an offgas containment system. Both LAW and HLW melter feed slurries were evaporated, calcined, and then melted at 1150 degrees C. The LAW and HLW glasses were heat-treated per a modeled centerline cooling curve for the LAW canister and HLW canister, respectively.
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| Total Pages | : 552 |
| Release | : 1981 |
| Genre | : Radioactive waste disposal |
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| Author | : International Atomic Energy Agency |
| Publisher | : |
| Total Pages | : 114 |
| Release | : 1992 |
| Genre | : Business & Economics |
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This report gives an up to date review of high level waste vitrification and storage facilities currently in an advanced stage of implementation.
| Author | : International Atomic Energy Agency |
| Publisher | : IAEA |
| Total Pages | : 188 |
| Release | : 2007 |
| Genre | : Business & Economics |
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Over the past decade significant progress has been achieved in the development of waste characterization and control procedures and equipment as a direct response to ever-increasing requirements for quality and reliability of information on waste characteristics. Failure in control procedures at any step can have important, adverse consequences and may result in producing waste packages which are not compliant with the waste acceptance criteria for disposal, thereby adversely impacting the repository. The information and guidance included in this publication corresponds to recent achievements and reflects the optimum approaches, thereby reducing the potential for error and enhancing the quality of the end product. -- Publisher's description.
| Author | : Pascal Richet |
| Publisher | : John Wiley & Sons |
| Total Pages | : 1568 |
| Release | : 2021-02-05 |
| Genre | : Technology & Engineering |
| ISBN | : 1118799399 |
This Encyclopedia begins with an introduction summarizing itsscope and content. Glassmaking; Structure of Glass, GlassPhysics,Transport Properties, Chemistry of Glass, Glass and Light,Inorganic Glass Families, Organic Glasses, Glass and theEnvironment, Historical and Economical Aspect of Glassmaking,History of Glass, Glass and Art, and outlinepossible newdevelopments and uses as presented by the best known people in thefield (C.A. Angell, for example). Sections and chapters arearranged in a logical order to ensure overall consistency and avoiduseless repetitions. All sections are introduced by a briefintroduction and attractive illustration. Newly investigatedtopics will be addresses, with the goal of ensuring that thisEncyclopedia remains a reference work for years to come.
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| Total Pages | : 10 |
| Release | : 1994 |
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Radioactive wastes on the Hanford Site are going to be permanently disposed of by incorporation into a durable glass. These wastes will be separated into low and high-level portions, and then vitrified. The low-level waste (LLW) is water soluble. Its vitrifiable part (other than off-gas) contains approximately 80 wt% Na2O, the rest being Al2O3, P2O5, K2O, and minor components. The challenge is to formulate durable LLW glasses with as high Na2O content as possible by optimizing the additions of SiO2, Al2O3, B2O3, CaO, and ZrO2. This task will not be simple, considering the non-linear and interactive nature of glass properties as a function of composition. Once developed, the LLW glass, being similar in composition to commercial glasses, is unlikely to cause major processing problems, such as crystallization or molten salt segregation. For example, inexpensive LLW glass can be produced in a high-capacity Joule-heated melter with a cold cap to minimize volatilization. The high-level waste (HLW) consists of water-insoluble sludge (Fe2O3, Al2O3, ZrO2, Cr2O3, NiO, and others) and a substantial water-soluble residue (Na2O). Most of the water-insoluble components are refractory; i.e., their melting points are above the glass melting temperature. With regard to product acceptability, the maximum loading of Hanford HLW in the glass is limited by product durability, not by radiolytic heat generation. However, this maximum may not be achievable because of technological constraints imposed by melter feed rheology, frit properties, and glass melter limits. These restrictions are discussed in this paper. 38 refs.
