Evaluation of interim and final waste forms for the newly generated liquid low-level waste flowsheet

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The purpose of this review is to evaluate the final forms that have been proposed for radioactive-containing solid wastes and to determine their application to the solid wastes that will result from the treatment of newly generated liquid low-level waste (NGLLLW) and Melton Valley Storage Tank (MVST) supernate at the Oak Ridge National Laboratory (ORNL). Since cesium and strontium are the predominant radionuclides in NGLLLW and MVST supernate, this review is focused on the stabilization and solidification of solid wastes containing these radionuclides in cement, glass, and polymeric materials-the principal waste forms that have been tested with these types of ... continued below

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87 p.

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Abotsi, G.M.K.; Bostick, D.T. & Beck, D.E. May 1, 1996.

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Description

The purpose of this review is to evaluate the final forms that have been proposed for radioactive-containing solid wastes and to determine their application to the solid wastes that will result from the treatment of newly generated liquid low-level waste (NGLLLW) and Melton Valley Storage Tank (MVST) supernate at the Oak Ridge National Laboratory (ORNL). Since cesium and strontium are the predominant radionuclides in NGLLLW and MVST supernate, this review is focused on the stabilization and solidification of solid wastes containing these radionuclides in cement, glass, and polymeric materials-the principal waste forms that have been tested with these types of wastes. Several studies have shown that both cesium and strontium are leached by distilled water from solidified cement, although the leachabilities of cesium are generally higher than those of strontium under similar conditions. The situation is exacerbated by the presence of sulfates in the solution, as manifested by cracking of the grout. Additives such as bentonite, blast-furnace slag, fly ash, montmorillonite, pottery clay, silica, and zeolites generally decrease the cesium and strontium release rates. Longer cement curing times (>28 d) and high ionic strengths of the leachates, such as those that occur in seawater, also decrease the leach rates of these radionuclides. Lower cesium leach rates are observed from vitrified wastes than from grout waste forms. However, significant quantities of cesium are volatilized due to the elevated temperatures required to vitrify the waste. Hence, vitrification will generally require the use of cleanup systems for the off-gases to prevent their release into the atmosphere.

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87 p.

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INIS; OSTI as DE96011591

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  • Other Information: PBD: May 1996

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  • Other: DE96011591
  • Report No.: ORNL/TM--13028
  • Grant Number: AC05-96OR22464
  • DOI: 10.2172/245580 | External Link
  • Office of Scientific & Technical Information Report Number: 245580
  • Archival Resource Key: ark:/67531/metadc673383

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

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  • May 1, 1996

Added to The UNT Digital Library

  • June 29, 2015, 9:42 p.m.

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  • Jan. 21, 2016, 8:21 p.m.

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Abotsi, G.M.K.; Bostick, D.T. & Beck, D.E. Evaluation of interim and final waste forms for the newly generated liquid low-level waste flowsheet, report, May 1, 1996; Tennessee. (digital.library.unt.edu/ark:/67531/metadc673383/: accessed October 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.