Certain waste streams of the US DOE contain radioactive refractory oxides and other components like aluminum zirconium and chromium, which present difficulties during their processing and immobilization. The vitrification of such waste in joule-heated melters at high waste loading is possible only at a temperature exceeding 1150°C. The Khlopin Radium Institute (St.-Petersburg, Russia) jointly with the US Department of Energy has performed a feasibility study on the suitability of the Cold-Crucible Induction Heated Melter (CCIM) technology for the single-stage solidification of a surrogate sludge (C-106/AY-102 HLW Simulant), similar in composition to the High Level Waste (HLW) found at DOE’s Hanford Site (Richland, USA). During the experiments, slurry of simulated sludge and glass formers was metered directly to the CCIM, melted, and the glass product was poured from the melter. The melts were conducted at a mean melt temperature of 1350°C. The experiments produced borosilicate glass wasteforms with a waste oxide loading of 70 weight percent. According to the X-Ray diffraction analysis, the final product had a glass-crystalline structure. The crystalline phase was represented by spinel, (Fe,Mn)Fe2O4, uniformly distributed over the wasteform. The chemical durability of the samples was tested by the Product Consistency Test (PCT), and was considered durable according to the DOE specifications for HLW. In the course of the experiments, data were accumulated on the specific electric power consumption and the throughput of the facility.
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ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation
September 21–25, 2003
Oxford, England
Conference Sponsors:
- Nuclear Engineering Division and Environmental Engineering Division
ISBN:
0-7918-3732-7
PROCEEDINGS PAPER
Vitrification of DOE Simulated Radioactive Waste by Induction-Heated Cold-Crucible Melter Technology Available to Purchase
A. S. Aloy,
A. S. Aloy
V. G. Khlopin Radium Institute, St. Petersburg, Russia
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R. A. Soshnikov,
R. A. Soshnikov
V. G. Khlopin Radium Institute, St. Petersburg, Russia
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D. B. Lopukh,
D. B. Lopukh
Electrotechnical University, St. Petersburg, Russia
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D. F. Bickford,
D. F. Bickford
Westinghouse Savannah River Company, Aiken, SC
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C. C. Herman,
C. C. Herman
Westinghouse Savannah River Company, Aiken, SC
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E. W. Holtzsheiter,
E. W. Holtzsheiter
Westinghouse Savannah River Company, Aiken, SC
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R. W. Goles
R. W. Goles
Pacific Northwest National Laboratory, Richland, WA
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A. S. Aloy
V. G. Khlopin Radium Institute, St. Petersburg, Russia
R. A. Soshnikov
V. G. Khlopin Radium Institute, St. Petersburg, Russia
D. B. Lopukh
Electrotechnical University, St. Petersburg, Russia
D. F. Bickford
Westinghouse Savannah River Company, Aiken, SC
C. C. Herman
Westinghouse Savannah River Company, Aiken, SC
E. W. Holtzsheiter
Westinghouse Savannah River Company, Aiken, SC
R. W. Goles
Pacific Northwest National Laboratory, Richland, WA
Paper No:
ICEM2003-4907, pp. 1599-1603; 5 pages
Published Online:
February 24, 2009
Citation
Aloy, AS, Soshnikov, RA, Lopukh, DB, Bickford, DF, Herman, CC, Holtzsheiter, EW, & Goles, RW. "Vitrification of DOE Simulated Radioactive Waste by Induction-Heated Cold-Crucible Melter Technology." Proceedings of the ASME 2003 9th International Conference on Radioactive Waste Management and Environmental Remediation. 9th ASME International Conference on Radioactive Waste Management and Environmental Remediation: Volumes 1, 2, and 3. Oxford, England. September 21–25, 2003. pp. 1599-1603. ASME. https://doi.org/10.1115/ICEM2003-4907
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