Materials performance in a high-level radioactive waste vitrification system

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The Defense Waste Processing Facility (DWPF) is a Department of Energy Facility designed to vitrify highly radioactive waste. An extensive materials evaluation program has been completed on key components in the DWPF after twelve months of operation using nonradioactive simulated wastes. Results of the visual inspections of the feed preparation system indicate that the system components, which were fabricated from Hastelloy C-276, should achieve their design lives. Significant erosion was observed on agitator blades that process glass frit slurries; however, design modifications should mitigate the erosion. Visual inspections of the DWPF melter top head and off gas components, which were ... continued below

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Imrich, K.J. & Chandler, G.T. June 17, 1996.

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The Defense Waste Processing Facility (DWPF) is a Department of Energy Facility designed to vitrify highly radioactive waste. An extensive materials evaluation program has been completed on key components in the DWPF after twelve months of operation using nonradioactive simulated wastes. Results of the visual inspections of the feed preparation system indicate that the system components, which were fabricated from Hastelloy C-276, should achieve their design lives. Significant erosion was observed on agitator blades that process glass frit slurries; however, design modifications should mitigate the erosion. Visual inspections of the DWPF melter top head and off gas components, which were fabricated from Inconel 690, indicated that varying degrees of degradation occurred. Most of the components will perform satisfactorily for their two year design life. The components that suffered significant attack were the borescopes, primary film cooler brush, and feed tubes. Changes in the operation of the film cooler brush and design modifications to the feed tubes and borescopes is expected to extend their service lives to two years. A program to investigate new high temperature engineered materials and alloys with improved oxidation and high temperature corrosion resistance will be initiated.

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20 p.

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INIS; OSTI as DE97060032

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  • 98. annual meeting of the American Ceramic Society, Indianapolis, IN (United States), 14-17 Apr 1996

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  • Other: DE97060032
  • Report No.: WSRC-MS--96-0356
  • Report No.: CONF-9604124--16
  • Grant Number: AC09-89SR18035
  • Office of Scientific & Technical Information Report Number: 399340
  • Archival Resource Key: ark:/67531/metadc680276

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Office of Scientific & Technical Information Technical Reports

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  • June 17, 1996

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  • July 25, 2015, 2:20 a.m.

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  • Feb. 9, 2016, 8:54 p.m.

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Imrich, K.J. & Chandler, G.T. Materials performance in a high-level radioactive waste vitrification system, article, June 17, 1996; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc680276/: accessed November 12, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.