Advanced Mixed Waste Treatment Project melter system preliminary design technical review meeting

Eddy, T.L.; Raivo, B.D.; Soelberg, Nick; Wiersholm, O.

doi:10.2172/114589

Cited by 4 publications

(5 citation statements)

References 4 publications

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“…In the melting of radioactive aluminum scrap, fluxes have been widely used for high thermal conductivity, high thermal capacity, low density, moderate viscosity, high electrical conductivity and mutual miscibility [10,16]. Alkali metal halides are the major components used as the flux for an aluminum melting.…”

Section: Methodsmentioning

confidence: 99%

Characteristics of a nuclides distribution during a melt decontamination of radioactive aluminum wastes

Min

Choi

et al. 2008

Korean J. Chem. Eng.

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The characteristics of an aluminum melting and the distribution of surrogate nuclide have been investigated in a muffle furnace and a lab-scale arc furnace as part of the fundamental research for a melting of the metallic wastes generated by dismantling research reactors. The melting of aluminum was carried out with the use of surrogate nuclides such as cobalt, cesium, and strontium, and fluxes such as NaCl-KCl-Na 3 AlF 6 (flux A), NaCl-NaF-KF (flux B), CaF 2 (flux C), and LiF-KCl-BaCl 2 (flux D). The effects of the melting temperature and the type of flux on the melting of the aluminum and the surrogate nuclide distribution in the ingot, slag, and dust phase were investigated in a muffle furnace. The addition of the flux increased the fluidity of the aluminum melt, which has a slight difference according to the type of fluxes, and the amounts of the slag generated during the melting with the flux types B and C were larger than those with flux types A and D. The results of the XRD analysis showed that the surrogate nuclides move into the slag, which can be easily separated from the melt, and then they combine with the aluminum oxide to form a more stable compound. The remaining cobalt in the ingot phase was less than 20% and the others were transferred into the slag and dust. A removal efficiency of more than 99.5% for cesium and strontium from the ingot phase could be achieved. Similar results for the slag formation and the distribution of the surrogate nuclides were obtained in a DC graphite arc melting system. Therefore, it is expected that a greater part of the aluminum wastes generated from the retired research reactors can be recycled or their volume reduced to be disposed of by melting.

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Section: Methodsmentioning

confidence: 99%

Characteristics of a nuclides distribution during a melt decontamination of radioactive aluminum wastes

Min

Choi

et al. 2008

Korean J. Chem. Eng.

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“…Joule heated melting (JHM) processes have been used for decades in the glass manufacturing industry and for treating high level radioactive wastes CRC Press 2001). Plasma arc melting has been used worldwide for decades in the steel and specialty metals industries, and has been studied and used to a limited degree in the U.S. and worldwide for waste treatment since the 1980's by the DOE, the U.S. Department of Defense, the U.S. EPA, the American Society of Mechanical Engineers, the U.S. Bureau of Mines (now combined with the DOE), universities such as Massachusetts Institute of Technology, and several private companies, and several foreign national entities (Eddy 1994, Soelberg 1997, Zaghloul 1997. The integration of joule heated melter (JHM) and plasma arc melter technologies in the PEM TM process, patented by IET, is designed to optimize the capabilities of both melting techniques to provide an effective and controllable process for treating a wide variety of waste materials including solid and liquid hazardous, municipal, hospital, radioactive, and mixed wastes.…”

Section: Iet Pem Tm Backgroundmentioning

confidence: 99%

environmental technology

2014

Dictionary Geotechnical Engineering/Wörterbuch GeoTechnik

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This Technology Verification report describes the nature and scope of the environmental evaluation of the performance of the Plasma Enhanced Melter TM (PEM™) system for waste treatment. The evaluation was conducted through a cooperative program established in 1998 between the Washington State Department of Ecology (WSDOE), Integrated Environmental Technology Inc. (IET), Allied Technology Group (ATG) and the Civil Engineering Research Foundation (CERF). The goal of this report is to provide potential users and purchasers of the PEM TM system with information they need to make more informed decisions regarding the performance of PEM TM as an equivalent or alternative to incineration for treating hazardous waste. Library of Congress Cataloguing-in-Publication DataEnvironmental technology verification report for the plasma enhanced melter / prepared by the Environmental Technology Evaluation Center (EvTEC), a service of the Civil Engineering Research Foundation (CERF). The material presented in this publication has been prepared in accordance with generally recognized engineering principles and practices, and is for general information only. This information should not be used without first securing competent advice with respect to its suitability for any general or specific application. The contents of this publication are not intended to be and should not be construed to be a standard of the American Society of Civil Engineers (ASCE), or its affiliate, CERF/IIEC, and are not intended for use as a reference in purchase specifications, contracts, regulations, statutes, or any other legal document. No reference made in this publication to any specific method, product, process, or service constitutes or implies an endorsement, recommendation, or warranty thereof by ASCE and CERF/IIEC.ASCE and CERF/IIEC make no representation or warranty of any kind, whether expressed or implied, concerning the accuracy, completeness, suitability, or utility of any information, apparatus, product, or process discussed in this publication, and assumes no liability thereof. Anyone utilizing this information assumes all liability arising from such use, including, but not limited to infringement of any patent or patents. Tables Table EV-1. Offgas measurement results from the tests Table 1.Offgas measurements performed during PEM™ tests Table 2.Feedrates, feed compositions, and key operating conditions for the tests Table 3.Effluent offgas conditions measured during the tests Table 4. D/F emissions measured during the tests Table 5.PAH emissions measured during the tests Table 6. PCB emissions measured during the tests Table 7.SVOC emissions measured during the Circuitboard Test Table 8.Summarized VOC emission measurements from the EvTEC and other tests Table 9.Destruction amd removal efficiency from the Equivalency Test for spiked PODCs Table 10.Metal emissions measured during the tests Table 11.Additives in the methanol feed used in the Equivalency Test Table 12.Composition of the circuitboard fabrication waste Table 13.Compos...

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“…Radioactive wastes require long-term stabilization and disposal, either of the waste itself or of the residue resulting from any treatment required. 2 Low-level radioactive waste (LLW) is often incinerated prior to ash stabilization to reduce volume. Treatment systems are usually small in size.…”

Section: Input Waste Streamsmentioning

confidence: 99%

“…A more detailed comparison of PTM and GAM is given elsewhere. 1,2,8 The IWS could be any of those shown in Table I; here, MSW is used as a broad example. Process temperatures can vary depending on the waste.…”

Section: Input Waste Streamsmentioning

confidence: 99%