Nuclear material estimation and uncertainties for the spent fuel treatment at FCF
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 and 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
Availability note (English)
Available from INIS in electronic form; Also available from OSTI as DE00011909; PURL: https://www.osti.gov/servlets/purl/11909-sqfCIg/webviewable/Files
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Additional details
Identifiers
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- ANL/RA/CP--99677
Conference
- Title
- 40. Annual Meeting of the Institute of Nuclear Materials Management (INMM)
- Dates
- 25-29 Jul 1999
- Place
- Phoenix, AZ (United States)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 32065047
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S98: NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DATA COVARIANCES; EBR-2 REACTOR; FUEL REPROCESSING PLANTS; MEASURING METHODS; NUCLEAR MATERIALS MANAGEMENT; SAMPLING; SPENT FUELS
- Descriptors DEC
- BREEDER REACTORS; ENERGY SOURCES; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUELS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; MANAGEMENT; MATERIALS; NUCLEAR FACILITIES; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SODIUM COOLED REACTORS
Optional Information
- Contract/Grant/Project number
- W-31109-ENG-38
- Funding organization
- US Department of Energy (United States)