Dry Processing of Used Nuclear Fuel Metadata

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Title

  • Main Title Dry Processing of Used Nuclear Fuel

Creator

  • Author: Goff, K. M.
    Creator Type: Personal
  • Author: Simpson, M. F.
    Creator Type: Personal

Contributor

  • Sponsor: United States. Office of Nuclear Energy, Science, and Technology.
    Contributor Type: Organization
    Contributor Info: DOE - NE

Publisher

  • Name: Idaho National Laboratory
    Place of Publication: [Idaho]
    Additional Info: INL

Date

  • Creation: 2009-09-01

Language

  • English

Description

  • Content Description: Dry (non-aqueous) separations technologies have been used for treatment of used nuclear fuel since the 1960s, and they are still being developed and demonstrated in many countries. Dry technologies offer potential advantages compared to traditional aqueous separations including: compactness, resistance to radiation effects, criticality control benefits, compatibility with advanced fuel types, and ability to produce low purity products. Within the Department of Energy’s Advanced Fuel Cycle Initiative, an electrochemical process employing molten salts is being developed for recycle of fast reactor fuel and treatment of light water reactor oxide fuel to produce a feed for fast reactors. Much of the development of this technology is based on treatment of used Experimental Breeder Reactor II (EBR-II) fuel, which is metallic. Electrochemical treatment of the EBR-II fuel has been ongoing in the Fuel Conditioning Facility, located at the Materials and Fuel Complex of Idaho National Laboratory since 1996. More than 3.8 metric tons of heavy metal of metallic fast reactor fuel have been treated using this technology. This paper will summarize the status of electrochemical development and demonstration activities with used nuclear fuel, including high-level waste work. A historic perspective on the background of dry processing will also be provided.

Subject

  • Keyword: Criticality
  • Keyword: Used Nuclear Fuel
  • Keyword: Processing
  • Keyword: Oxides
  • Keyword: Dry Processing
  • Keyword: Heavy Metals
  • Keyword: Fuel Cycle
  • Keyword: Wastes
  • Keyword: Radiation Effects
  • STI Subject Categories: 11 Nuclear Fuel Cycle And Fuel Materials
  • Keyword: Nuclear Fuels
  • Keyword: Molten Salts
  • Keyword: Breeder Reactors
  • Keyword: Water Dry Processing
  • Keyword: Fast Reactors
  • Keyword: Idaho
  • Keyword: Compatibility
  • Keyword: Metrics

Source

  • Conference: Global 2009,Paris, France,09/06/2009,09/11/2009

Collection

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

Institution

  • Name: UNT Libraries Government Documents Department
    Code: UNTGD

Resource Type

  • Article

Format

  • Text

Identifier

  • Report No.: INL/CON-09-15984
  • Grant Number: DE-AC07-05ID14517
  • Office of Scientific & Technical Information Report Number: 968661
  • Archival Resource Key: ark:/67531/metadc927150
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