DEFENSE HIGH LEVEL WASTE GLASS DEGRADATION Metadata

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Title

  • Main Title DEFENSE HIGH LEVEL WASTE GLASS DEGRADATION

Creator

  • Author: Ebert, W.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Department of Energy.
    Contributor Type: Organization

Publisher

  • Name: United States. Department of Energy. Office of Scientific and Technical Information.
    Place of Publication: Oak Ridge, Tennessee
    Additional Info: Office of Scientific and Technical Information, Oak Ridge, TN

Date

  • Creation: 2001-09-20

Language

  • English

Description

  • Content Description: The purpose of this Analysis/Model Report (AMR) is to document the analyses that were done to develop models for radionuclide release from high-level waste (HLW) glass dissolution that can be integrated into performance assessment (PA) calculations conducted to support site recommendation and license application for the Yucca Mountain site. This report was developed in accordance with the ''Technical Work Plan for Waste Form Degradation Process Model Report for SR'' (CRWMS M&O 2000a). It specifically addresses the item, ''Defense High Level Waste Glass Degradation'', of the product technical work plan. The AP-3.15Q Attachment 1 screening criteria determines the importance for its intended use of the HLW glass model derived herein to be in the category ''Other Factors for the Postclosure Safety Case-Waste Form Performance'', and thus indicates that this factor does not contribute significantly to the postclosure safety strategy. Because the release of radionuclides from the glass will depend on the prior dissolution of the glass, the dissolution rate of the glass imposes an upper bound on the radionuclide release rate. The approach taken to provide a bound for the radionuclide release is to develop models that can be used to calculate the dissolution rate of waste glass when contacted by water in the disposal site. The release rate of a particular radionuclide can then be calculated by multiplying the glass dissolution rate by the mass fraction of that radionuclide in the glass and by the surface area of glass contacted by water. The scope includes consideration of the three modes by which water may contact waste glass in the disposal system: contact by humid air, dripping water, and immersion. The models for glass dissolution under these contact modes are all based on the rate expression for aqueous dissolution of borosilicate glasses. The mechanism and rate expression for aqueous dissolution are adequately understood; the analyses in this AMR were conducted to provide models and parameter values that can be used to calculate the dissolution rates for the different modes of water contact. The analyses were conducted to identify key aspects of the mechanistic model for glass dissolution to be included in the abstracted models used for PA calculations, evaluate how the models can be used to calculate bounding values of the glass dissolution rates under anticipated water contact modes in the disposal. system, and determine model parameter values for the range of potential waste glass compositions and anticipated environmental conditions. The analysis of a bounding rate also considered the effects of the buildup of glass corrosion products in the solution contacting the glass and potential effects of alteration phase formation. Note that application of the models and model parameter values is constrained to the anticipated range of HLW glass compositions and environmental conditions. The effects of processes inherent to exposure to humid air and dripping water were not modeled explicitly. Instead, the impacts of these processes on the degradation rate were taken into account by using empirically measured parameter values. These include the rates at which water sorbs onto the glass, drips onto the glass, and drips off of the glass. The dissolution rates of glasses that were exposed to humid air and dripping water measured in laboratory tests are used to estimate model parameter values for contact by humid air and dripping water in the disposal system.

Subject

  • Keyword: Surface Area
  • Keyword: License Applications
  • Keyword: Recommendations
  • Keyword: Waste Forms
  • Keyword: Yucca Mountain
  • Keyword: Dissolution
  • Keyword: Wastes
  • Keyword: Radioisotopes
  • Keyword: Glass
  • Keyword: Water
  • Keyword: Safety
  • STI Subject Categories: 12 Management Of Radioactive Wastes, And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: Buildup
  • Keyword: Corrosion Products
  • Keyword: Performance
  • Keyword: Borosilicate Glass

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.: ANL-EBS-MD-000016 REV 00 ICN 02
  • Grant Number: NA
  • DOI: 10.2172/861094
  • Office of Scientific & Technical Information Report Number: 861094
  • Archival Resource Key: ark:/67531/metadc781521