Pilot-scale equipment development for pyrochemical reduction of spent oxide fuel

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Argonne National Laboratory (ANL) has developed and is presently demonstrating the electrometallurgical conditioning of sodium-bonded spent metal fuel from Experimental Breeder Reactor II, resulting in uranium, ceramic, and metal waste forms. Equipment is being developed at ANL which will precondition irradiated oxide fuel and demonstrate the application of electrometallurgical conditioning to such non-metallic fuels as well. The oxide reduction process preconditions irradiated oxide fuel such that uranium and transuranic (TRU) constituents are chemically reduced into metallic form via a molten Li/LiCl-based reduction system. In this form the spent fuel is further conditioned in an electrorefiner and waste handling equipment, thereby ... continued below

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2 p.

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Herrmann, S.D.; King, R.W.; Durstine, K.R. & Eberl, C.S. July 1, 1998.

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  • Argonne National Laboratory
    Publisher Info: Argonne National Lab., Idaho Falls, ID (United States)
    Place of Publication: Idaho Falls, Idaho

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Description

Argonne National Laboratory (ANL) has developed and is presently demonstrating the electrometallurgical conditioning of sodium-bonded spent metal fuel from Experimental Breeder Reactor II, resulting in uranium, ceramic, and metal waste forms. Equipment is being developed at ANL which will precondition irradiated oxide fuel and demonstrate the application of electrometallurgical conditioning to such non-metallic fuels as well. The oxide reduction process preconditions irradiated oxide fuel such that uranium and transuranic (TRU) constituents are chemically reduced into metallic form via a molten Li/LiCl-based reduction system. In this form the spent fuel is further conditioned in an electrorefiner and waste handling equipment, thereby placing the uranium, TRU elements, and fissions products into stable forms suitable for placement in a long-term repository. Development of the Li/LiCl-based oxide reduction process has proceeded at lab- (nominally 50 grams of heavy metal (HM)) and engineering-scale (nominally 10-kg of HM) for unirradiated oxide fuel. The presentation described the process and equipment design for scale-up from lab- and engineering-scale reduction of unirradiated oxide fuel in gloveboxes to pilot-scale (up to 100-kg of HM) reduction of irradiated oxide fuel in a hot cell. [Abstract only.]

Physical Description

2 p.

Notes

INIS; OSTI as DE98057810

Source

  • 22. annual actinide separations conference, Chattanooga, TN (United States), 20-23 Apr 1998

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  • Other: DE98057810
  • Report No.: ANL/ED/CP--95729
  • Report No.: CONF-980452--
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 656564
  • Archival Resource Key: ark:/67531/metadc710875

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  • July 1, 1998

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  • Sept. 12, 2015, 6:31 a.m.

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  • May 16, 2016, 5:19 p.m.

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Herrmann, S.D.; King, R.W.; Durstine, K.R. & Eberl, C.S. Pilot-scale equipment development for pyrochemical reduction of spent oxide fuel, article, July 1, 1998; Idaho Falls, Idaho. (digital.library.unt.edu/ark:/67531/metadc710875/: accessed September 21, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.