Quantify Sodium Fluoride / Beryllium Fluoride Salt Properties for a Liquid Fueled Fluoride Molten Salt Reactor (CRADA C2018-18168 Final Report)

Technical Report · Tue Feb 02 00:00:00 EST 2021

DOI:https://doi.org/10.2172/1764854· OSTI ID:1764854

Rose, M. A. ^[1]; Wu, E. ^[1]; Lichtenstein, T. ^[1]; Krueger, J. ^[1]; Thomas, S. ^[1]; Williamson, M. A. ^[1]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)

ThorCon is developing a thermal thorium-uranium fueled molten salt reactor that uses a fuel salt consisting of NaF - BeF₂ - ThF₄ - UF₄ - UF₃, which uses 19.75% enriched uranium. It is not a breeder reactor but requires regular additions of fissile material. A thorough understanding of the thermophysical properties of the fuel salt at the beginning (BOL) and end (EOL) of its life is critical to establishing its thermal hydraulic behavior and enables ThorCon to design a system with the required natural convection. Experimentally determining the heat capacity and thermal conductivity of the fuel salt will provide data necessary for detailed system design and safety analysis.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE Office of Nuclear Energy (NE)
• Contributing Organization: ThorCon US, Inc.
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1764854
• Report Number(s): ANL/CFCT-C2018-18168; 165860; TRN: US2215126
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS