Combined Waste Form Cost Trade Study Metadata

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Title

  • Main Title Combined Waste Form Cost Trade Study

Creator

  • Author: Gombert, Dirk
    Creator Type: Personal
  • Author: Piet, Steve
    Creator Type: Personal
  • Author: Trickel, Timothy
    Creator Type: Personal
  • Author: Carter, Joe
    Creator Type: Personal
  • Author: Vienna, John
    Creator Type: Personal
  • Author: Ebert, Bill
    Creator Type: Personal
  • Author: Matthern, Gretchen
    Creator Type: Personal

Contributor

  • Sponsor: United States. Office of the Assistant Secretary for Nuclear Energy.
    Contributor Type: Organization
    Contributor Info: DOE - NE

Publisher

  • Name: Idaho National Laboratory
    Place of Publication: [Idaho Falls, Idaho]
    Additional Info: Idaho National Laboratory (INL)

Date

  • Creation: 2008-11-01

Language

  • English

Description

  • Content Description: A new generation of aqueous nuclear fuel reprocessing, now in development under the auspices of the DOE Office of Nuclear Energy (NE), separates fuel into several fractions, thereby partitioning the wastes into groups of common chemistry. This technology advance enables development of waste management strategies that were not conceivable with simple PUREX reprocessing. Conventional wisdom suggests minimizing high level waste (HLW) volume is desirable, but logical extrapolation of this concept suggests that at some point the cost of reducing volume further will reach a point of diminishing return and may cease to be cost-effective. This report summarizes an evaluation considering three groupings of wastes in terms of cost-benefit for the reprocessing system. Internationally, the typical waste form for HLW from the PUREX process is borosilicate glass containing waste elements as oxides. Unfortunately several fission products (primarily Mo and the noble metals Ru, Rh, Pd) have limited solubility in glass, yielding relatively low waste loading, producing more glass, and greater disposal costs. Advanced separations allow matching the waste form to waste stream chemistry, allowing the disposal system to achieve more optimum waste loading with improved performance. Metals can be segregated from oxides and each can be stabilized in forms to minimize the HLW volume for repository disposal. Thus, a more efficient waste management system making the most effective use of advanced waste forms and disposal design for each waste is enabled by advanced separations and how the waste streams are combined. This trade-study was designed to juxtapose a combined waste form baseline waste treatment scheme with two options and to evaluate the cost-benefit using available data from the conceptual design studies supported by DOE-NE.

Subject

  • Keyword: Reprocessing
  • Keyword: Nuclear Fuels
  • Keyword: Waste Management
  • Keyword: Waste Forms
  • Keyword: High Level Waste
  • Keyword: Repository
  • Keyword: Glass
  • Keyword: Purex Process
  • Keyword: Extrapolation
  • Keyword: Oxides
  • Keyword: Fission Products
  • STI Subject Categories: 12 Mgmt Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities
  • Keyword: Design
  • Keyword: Chemistry
  • Keyword: Solubility
  • Keyword: Spent Nuclear Fuel
  • Keyword: Waste Processing High Level Waste
  • 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.: INL/EXT-08-14993
  • Grant Number: DE-AC07-99ID-13727
  • DOI: 10.2172/946848
  • Office of Scientific & Technical Information Report Number: 946848
  • Archival Resource Key: ark:/67531/metadc895327