Sulfur Partitioning During Vitrification of INEEL Sodium Bearing Waste: Status Report Metadata

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Title

  • Main Title Sulfur Partitioning During Vitrification of INEEL Sodium Bearing Waste: Status Report

Creator

  • Author: Darab, John G.
    Creator Type: Personal
  • Author: Macisaac, Brett D.
    Creator Type: Personal
  • Author: Russell, Renee L.
    Creator Type: Personal
  • Author: Smith, Harry D.
    Creator Type: Personal
  • Author: Vienna, John D.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization
    Contributor Info: US Department of Energy (United States)

Publisher

  • Name: Pacific Northwest National Laboratory (U.S.)
    Place of Publication: Richland, Washington
    Additional Info: Pacific Northwest National Lab., Richland, WA (United States)

Date

  • Creation: 2001-07-31

Language

  • English

Description

  • Content Description: The sodium bearing tank waste (SBW) at Idaho National Engineering and Environmental Laboratory (INEEL) contains high concentrations of sulfur (roughly 5 mass% of SO3 on a nonvolatile oxide basis). The amount of sulfur that can be feed to the melter will ultimately determine the loading of SBW in glass produced by the baseline (low-temperature, joule-heated, liquid-fed, ceramic-lined) melter. The amount of sulfur which can be fed to the melter is determined by several major factors including: the tolerance of the melter for an immiscible salt layer accumulation, the solubility of sulfur in the glass melt, the fraction of sulfur removed to the off-gas, and the incorporation of sulfur into the glass up to it?s solubility limit. This report summarizes the current status of testing aimed at determining the impacts of key chemical and physical parameters on the partitioning of sulfur between the glass, a molten salt, and the off-gas.
  • Physical Description: vp.

Subject

  • Keyword: Partition
  • Keyword: Radioactive Waste Processing
  • Keyword: Sodium Compounds
  • Keyword: Solubility
  • Keyword: Glass
  • Keyword: Molten Salts
  • STI Subject Categories: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: Sulfur
  • Keyword: Idaho National Engineering Laboratory
  • Keyword: Vitrification

Source

  • Other Information: PBD: 31 Jul 2001

Collection

  • Name: Office of Scientific & Technical Information Technical Reports
    Code: OSTI

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report

Format

  • Text

Identifier

  • Report No.: PNNL-13588
  • Report No.: EW4010000
  • Grant Number: AC06-76RLO1830
  • DOI: 10.2172/786800
  • Office of Scientific & Technical Information Report Number: 786800
  • Archival Resource Key: ark:/67531/metadc723302