Nuclear material estimation and uncertainties for the spent fuel treatment at FCF.

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Spent fuel from the Experimental Breeder Reactor-II (EBR-II) is treated at the Fuel Conditioning Facility (FCF) located at Argonne National Laboratory-West (ANL-W). A number of sensitive nuclear material streams are present in the facility, which mainly include material in the input spent fuel, the element chopper, the electrorefiner, the cathode processor, and the casting furnace. Different types of measurements and calculations are performed in order to estimate the amount of material in those streams. There are three basic types of measurements: weight, elemental and isotopic fractions, and liquid level measurements. Materials in some streams are determined using validated models, which ... continued below

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10 p.

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Battisti, T.; Bucher, R. G.; Krsul, J.; Mariani, R. D.; McKnight, R. D.; Vaden, D. et al. July 27, 1999.

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Description

Spent fuel from the Experimental Breeder Reactor-II (EBR-II) is treated at the Fuel Conditioning Facility (FCF) located at Argonne National Laboratory-West (ANL-W). A number of sensitive nuclear material streams are present in the facility, which mainly include material in the input spent fuel, the element chopper, the electrorefiner, the cathode processor, and the casting furnace. Different types of measurements and calculations are performed in order to estimate the amount of material in those streams. There are three basic types of measurements: weight, elemental and isotopic fractions, and liquid level measurements. Materials in some streams are determined using validated models, which include the mass and composition of the input spent fuel. This paper describes the different streams of sensitive nuclear material for the facility, and the methods for their measurements or estimation as part of the MC&A system at FCF. It also describes the analytical and sampling uncertainties associated with those measurements and estimates, which are required for the facility variance propagation calculations.

Physical Description

10 p.

Notes

INIS; OSTI as DE00011909

Medium: P; Size: 10 pages

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  • INMM 40th Annual Meeting, Phoenix, AZ (US), 07/25/1999--07/29/1999

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  • Report No.: ANL/RA/CP-99677
  • Grant Number: W-31109-ENG-38
  • Office of Scientific & Technical Information Report Number: 11909
  • Archival Resource Key: ark:/67531/metadc628534

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Office of Scientific & Technical Information Technical Reports

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  • July 27, 1999

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  • June 16, 2015, 7:43 a.m.

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  • April 6, 2017, 6:49 p.m.

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Battisti, T.; Bucher, R. G.; Krsul, J.; Mariani, R. D.; McKnight, R. D.; Vaden, D. et al. Nuclear material estimation and uncertainties for the spent fuel treatment at FCF., article, July 27, 1999; Illinois. (digital.library.unt.edu/ark:/67531/metadc628534/: accessed October 17, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.