Comparative Waste Forms Study

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A number of alternative process and waste form options exist for the immobilization of nuclear wastes. Although data exists on the characterization of these alternative waste forms, a straightforward comparison of product properties is difficult, due to the lack of standardized testing procedures. The characterization study described in this report involved the application of the same volatility, mechanical strength and leach tests to ten alternative waste forms, to assess product durability. Bulk property, phase analysis and microstructural examination of the simulated products, whose waste loading varied from 5% to 100% was also conducted. The specific waste forms investigated were as ... continued below

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Wald, J. W.; Lokken, R. O.; Shade, J. W. & Rusin, J. M. December 1980.

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  • Pacific Northwest Laboratory
    Publisher Info: Battelle Pacific Northwest Labs., Richland, WA (USA)
    Place of Publication: Richland, Washington

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Description

A number of alternative process and waste form options exist for the immobilization of nuclear wastes. Although data exists on the characterization of these alternative waste forms, a straightforward comparison of product properties is difficult, due to the lack of standardized testing procedures. The characterization study described in this report involved the application of the same volatility, mechanical strength and leach tests to ten alternative waste forms, to assess product durability. Bulk property, phase analysis and microstructural examination of the simulated products, whose waste loading varied from 5% to 100% was also conducted. The specific waste forms investigated were as follows: Cold Pressed and Sintered PW-9 Calcine; Hot Pressed PW-9 Calcine; Hot Isostatic Pressed PW-9 Calcine; Cold Pressed and Sintered SPC-5B Supercalcine; Hot Isostatic pressed SPC-5B Supercalcine; Sintered PW-9 and 50% Glass Frit; Glass 76-68; Celsian Glass Ceramic; Type II Portland Cement and 10% PW-9 Calcine; and Type II Portland Cement and 10% SPC-5B Supercalcine. Bulk property data were used to calculate and compare the relative quantities of waste form volume produced at a spent fuel processing rate of 5 metric ton uranium/day. This quantity ranged from 3173 L/day (5280 Kg/day) for 10% SPC-5B supercalcine in cement to 83 L/day (294 Kg/day) for 100% calcine. Mechanical strength, volatility, and leach resistance tests provide data related to waste form durability. Glass, glass-ceramic and supercalcine ranked high in waste form durability where as the 100% PW-9 calcine ranked low. All other materials ranked between these two groupings.

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NTIS, PC A04/MF A01.

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  • Report No.: PNL-3516
  • Grant Number: AC06-76RL01830
  • DOI: 10.2172/7018788 | External Link
  • Office of Scientific & Technical Information Report Number: 7018788
  • Archival Resource Key: ark:/67531/metadc1198586

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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Creation Date

  • December 1980

Added to The UNT Digital Library

  • July 2, 2018, 10:52 p.m.

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  • March 7, 2019, 1:08 p.m.

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Wald, J. W.; Lokken, R. O.; Shade, J. W. & Rusin, J. M. Comparative Waste Forms Study, report, December 1980; Richland, Washington. (https://digital.library.unt.edu/ark:/67531/metadc1198586/: accessed March 24, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.