FCF metallic waste data uncertainty analysis.

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Description

Metallic waste is a residual of the electrometallurgical treatment of the Experimental Breeder Reactor II (EBR-II) spent fuel. The treatment is based on electrorefining the fuel in molten salt, and currently it remains in the demonstration phase at the Fuel Conditioning Facility (FCF) at Argonne National Laboratory-West (ANL-W). A reference metallic waste form is produced by mixing 15% zirconium with the stainless steel cladding hulls, which remain in the fuel dissolution baskets (FDB's) after electrorefining, to form a metal alloy. Estimates of uranium in this waste form are of importance to both operations and sensitive materials control and accountability (MC ... continued below

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7 p.

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Yacout, A. M. February 2, 1998.

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Description

Metallic waste is a residual of the electrometallurgical treatment of the Experimental Breeder Reactor II (EBR-II) spent fuel. The treatment is based on electrorefining the fuel in molten salt, and currently it remains in the demonstration phase at the Fuel Conditioning Facility (FCF) at Argonne National Laboratory-West (ANL-W). A reference metallic waste form is produced by mixing 15% zirconium with the stainless steel cladding hulls, which remain in the fuel dissolution baskets (FDB's) after electrorefining, to form a metal alloy. Estimates of uranium in this waste form are of importance to both operations and sensitive materials control and accountability (MC and A). Accurate estimates of the uranium in this product provide important information regarding the dissolution of uranium and the efficiency of the electrorefining process. Under certain operating conditions, non-negligible amounts of uranium were found in this stream, which made it an area of interest for MC and A. The estimates of uranium in this waste stream are currently provided through analysis of cladding hulls samples. The collected cladding hulls data and the errors associated with the data are discussed here, in addition to the effects of these errors on the overall facility ID variance.

Physical Description

7 p.

Notes

INIS; OSTI as DE00010619

Medium: P; Size: 7 pages

Source

  • American Nuclear Society 3rd Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC (US), 09/08/1998--09/11/1998

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  • Report No.: ANL/RA/CP-95514
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 10619
  • Archival Resource Key: ark:/67531/metadc624387

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • February 2, 1998

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • April 11, 2017, 3:16 p.m.

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Yacout, A. M. FCF metallic waste data uncertainty analysis., article, February 2, 1998; Illinois. (digital.library.unt.edu/ark:/67531/metadc624387/: accessed November 17, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.