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FCF metallic waste data uncertainty analysis. [electronic resource]

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Bibliographic Details
Online Access:	Online Access
Corporate Author:	Argonne National Laboratory (Researcher)
Format:	Government Document Electronic eBook
Language:	English
Published:	Washington, D.C : Oak Ridge, Tenn. : United States. Dept. of Energy ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1998.
Subjects:	Ebr-2 Reactor. Spent Fuels. Stainless Steels. Waste Forms. Radioactive Waste Facilities. Electrorefining. Zirconium. Nuclear Materials Management. Uranium. Data Covariances. Nuclear Fuel Cycle And Fuel Materials. Nuclear Disarmament, Safeguards, And Physical Protection. Specific Nuclear Reactors And Associated Plants.

Description
Abstract:	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.
Item Description:	Published through the Information Bridge: DOE Scientific and Technical Information. 02/02/1998. "ANL/RA/CP-95514" American Nuclear Society 3rd Topical Meeting DOE Spent Nuclear Fuel and Fissile Materials Management, Charleston, SC (US), 09/08/1998--09/11/1998. Yacout, A. M.
Physical Description:	7 pages.