Melt Rate Testing for the DWPF: Summary of FY02 Testing Metadata

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  • Main Title Melt Rate Testing for the DWPF: Summary of FY02 Testing
  • Series Title Fiscal Year 2002


  • Author: Lorier, T.H.
    Creator Type: Personal


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


  • Name: Savannah River Site (S.C.)
    Place of Publication: South Carolina
    Additional Info: Savannah River Site (United States)


  • Creation: 2003-02-19


  • English


  • Content Description: A study performed in FY01 recommended that the Defense Waste Process Facility (DWPF) replace Frit 200 with Frit 320 for the processing of sludge batch 2 (SB2) to improve melt rate (Lambent et al., 2001) contingent upon additional testing which included slurry feeding. The FY02 melt rate program was developed to support this recommendation as well as to investigate alternative methods of improving melt rate above and beyond a change in frit composition. The integrated program was primarily based on a sound testing methodology from which the frit change was recommended. In addition, the program included the development of additional tools to provide further insight into melt rate enhancements. The overall strategy of the FY02 testing program was to design suites of melt rate tests based on recommendations from previous work that provided insight into other methods of improving melt rate for the DWPF. The objectives of the FY02 testing program included how melt rate might be influenced by increases in waste loading, differences in frit particle size, the use of batch chemicals rather than a pre-fabricated frit, and the impact of uranium. This report summarizes the equipment development and setup, procedures, and results of this testing, and includes recommendations on the processing of SB2 with Frit 320 and future research.
  • Physical Description: vp.


  • Keyword: Sludges
  • Keyword: Uranium
  • Keyword: Waste Forms
  • Keyword: Radioactive Waste Processing
  • Keyword: Melting
  • Keyword: Materials Testing
  • Keyword: Glass
  • STI Subject Categories: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: Particle Size


  • Other Information: PBD: 19 Feb 2003


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


  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Report


  • Text


  • Report No.: WSRC-TR-2002-00545
  • Grant Number: AC09-96SR18500
  • DOI: 10.2172/808203
  • Office of Scientific & Technical Information Report Number: 808203
  • Archival Resource Key: ark:/67531/metadc740722