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Showing 1 to 13 of 13 for “"FLiNaK"”.

  1. Experimental investigations of thermodynamic properties of the LiF –CsF binary system and FliNaK

    Generation IV nuclear power technologies, including various molten salt reactor designs are considered to accommodate growing energy needs with minimal impact on the environment. The development of the molten salt reactor class highly depends on understanding molten fluoride salt physicochemical …

    uoit Repository record for Experimental investigations of thermodynamic properties of the LiF –CsF binary system and FliNaK (opens in a new tab)

  2. One-dimensional single phase natural circulation model of FLiNaK in Molten Salt Loop

    … effects and thermal storage applications of FLiNaK. The model’s purpose is to help design the flow loop and future experiments. Generation IV reactors were compared to provide an overview of new reactor concepts with an in-depth review of the Molten Salt Reactor MSR type. The molten salt …

    uoit Repository record for One-dimensional single phase natural circulation model of FLiNaK in Molten Salt Loop (opens in a new tab)

  3. Investigation of corrosion mechanisms between molten eutectic FliNaK salt and 316L stainless steel

    Submission original under an indefinite embargo labeled 'Open Access'. The submission was exported from vireo on 2023-04-12 without embargo terms

    uiuc Repository record for Investigation of corrosion mechanisms between molten eutectic FliNaK salt and 316L stainless steel (opens in a new tab)

  4. Species Chemistry and Electrochemical Separation in Molten Fluoride Salt

    … products and corrosion products in molten FLiNaK salt (46.5LiF-11.5NaF-42KF mol%) which is the surrogate of the primary coolant candidate FLiBe (67LiF-33BeF2, mol%) for FHR. The main objective is to investigate the electrochemical behaviors of fission products and corrosion products in …

    vt Repository record for Species Chemistry and Electrochemical Separation in Molten Fluoride Salt (opens in a new tab)

  5. Decommissioning considerations for molten salt type reactors

    … systems were used: one for the synthesis of FLiNaK salt and the other for the remelting and drainage of residue FLiNaK from a Hastelloy-C276 segment. The results of these experiments have demonstrated that FLiNaK salt, given contact with atmospheric moisture, tends to change in condition over …

    uoit Repository record for Decommissioning considerations for molten salt type reactors (opens in a new tab)

  6. Accelerated atomistic prediction of structure, dynamics and material properties in molten salts

    … prototypical Flibe (66.6%LiF-33.3%BeF2), and Flinak (46.5%LiF-11.5NaF-42%KF). Predictions include thermophysical and transport properties such as bulk density, thermal expansion coefficient, bulk modulus, and diffusivity, which were compared to available experimental data.

    mit Repository record for Accelerated atomistic prediction of structure, dynamics and material properties in molten salts (opens in a new tab)

  7. Evaluating Fluoride Molten Salt Thermophysical Properties with Transient Grating Spectroscopy

    … measure the thermal conductivity of fluorides (FLiNaK). Results show a flat to slightly increasing thermal conductivity as a function of temperature (0.7086 + 0.0002 ⋅ T(oC) +/- 0.08 W/m-K). In addition to thermal conductivity, sound speed data as a function of temperature (2998 – 1.24 ⋅ T(oC) …

    mit Repository record for Evaluating Fluoride Molten Salt Thermophysical Properties with Transient Grating Spectroscopy (opens in a new tab)

  8. Separation and Properties of La₂O₃ in Molten LiF-NaF-KF Salt

    … In this study, the La₂O₃-LiF-NaF-KF (La₂O₃-FLiNaK) system is used to demonstrate impurity separation in molten fluoride salt. Since lanthanum oxide needs to be dissolved in the fluoride molten salt and studies in this field are still not complete, the solubility of lanthanum oxide in FLiNaK

    vt Repository record for Separation and Properties of La₂O₃ in Molten LiF-NaF-KF Salt (opens in a new tab)

  9. Telluridm-induced corrosion of structural alloys for nuclear applications in molten salts

    … alloy after its immersion in molten LiF-NaF-KF (FLiNaK) salt at 700 °C using scanning electron microscopy (SEM) and energy-dispersive x-ray spectroscopy (EDS), a consistent corrosion rate could not be determined for any of the alloys, nor could confident identification of telluride compounds …

    mit Repository record for Telluridm-induced corrosion of structural alloys for nuclear applications in molten salts (opens in a new tab)

  10. Natural convection of molten salt in laterally heated and top cooled vertical cylinders

    … characteristics within the molten salt FLiNaK (Prandtl number = 16) in a vertical three-dimensional cylindrical geometry are numerically studied. The cylinder is laterally heated with an isothermal cooling at the top and an insulated bottom. The effect of the Rayleigh number is …

    uiuc Repository record for Natural convection of molten salt in laterally heated and top cooled vertical cylinders (opens in a new tab)

  11. Thermal Properties of Candidate Coolant Salts

    … of verifying our methodology. Specifically, FLiNaK was used in the development of volume-height curves as calibration for density measurements. NaOH-KOH of four different compositions ( 0.5-0.5mol%, 0.55-0.45mol%, 0.6-0.4mol%, and 0.65-0.35 mol%) will be evaluated for their densities and heat …

    vt Repository record for Thermal Properties of Candidate Coolant Salts (opens in a new tab)

  12. Design Space Exploration for Salt Cooled Reactor Systems

    … type fuel; three coolant options: 1) FLiBe 2) FLiNaK and 3) NaF-ZrF4, and three fuel forms: 1) Uranium Dioxide (UO2), Uranium Carbide (UC), and Fully Ceramic Microencapsulated (FCM) fuel. A package of thermal-hydraulic operating domain search and design optimisation codes was created that can …

    cambridge Repository record for Design Space Exploration for Salt Cooled Reactor Systems (opens in a new tab)

  13. Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs

    … 200 kW. FLiBe with high enrichment in Li-7, and FLiNaK have been selected as the primary and secondary salts, respectively. A 16-MWth pebble bed core proposed by University of California at Berkeley (UCB) is adopted in the design. Shell-and-tube heat exchangers, based on Delaware Method have been …

    ohiolink Repository record for Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs (opens in a new tab)