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Showing 1 to 20 of 29 for “"Fluoride Salt"”.

  1. Species Chemistry and Electrochemical Separation in Molten Fluoride Salt

    Fluoride salt-cooled high-temperature reactor (FHR) is a safer and potentially less expensive alternative to light water reactor due to the low pressure of primary system, passive decay heat cooling system, chemically inert coolant salt, and high-temperature power cycle. However, one challenge …

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

  2. Developing a framework for thermodynamic measurements of fluoride salt nuclear fuel

    … as a primary coolant and a nuclear fuel, molten salt reactor development has been challenged with understanding the behavior of its complex fluoride solution under various conditions. Experimental thermodynamics can address part of this challenge by providing insights into the system’s behaviour, …

    uoit Repository record for Developing a framework for thermodynamic measurements of fluoride salt nuclear fuel (opens in a new tab)

  3. Fluoride-salt-cooled high-temperature reactor generative design optimization with evolutionary algorithms

    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 Fluoride-salt-cooled high-temperature reactor generative design optimization with evolutionary algorithms (opens in a new tab)

  4. Fluoride-salt-cooled high-temperature test reactor thermal-hydraulic licensing and uncertainty propagation analysis

    An important Fluoride-salt-cooled High-temperature Reactor (FHR) development step is to design, build, and operate a test reactor. Through a literature review, liquid-salt coolant thermophysical properties have been recommended along with their uncertainties of 2-20%. This study tackles determining …

    mit Repository record for Fluoride-salt-cooled high-temperature test reactor thermal-hydraulic licensing and uncertainty propagation analysis (opens in a new tab)

  5. Tritium thermal desorption testing of nuclear graphites irradiated at fluoride-salt-cooled high-temperature reactor conditions

    The Fluoride-Salt-Cooled High-Temperature Reactor (FHR) is a next-generation nuclear plant design that combines successfully demonstrated technologies from other advanced reactor concepts such as tristructural isotropic (TRISO) coated particle fuel, molten flibe salt (LiF-BeF2) coolant, and an …

    mit Repository record for Tritium thermal desorption testing of nuclear graphites irradiated at fluoride-salt-cooled high-temperature reactor conditions (opens in a new tab)

  6. Evaluation of an aluminum latent heat storage system for the fluoride-salt-cooled high-temperature reactor

    … with high-temperature heat sources, such as the Fluoride-Salt-Cooled High- Temperature Reactor, and the use of a metallic heat transfer fluid (HTF) allows for a high rate of heat transfer. In this thesis, a 0.993 GWh thermal battery (ALTA) comprised of an aluminum PCM and sodium HTF is designed …

    mit Repository record for Evaluation of an aluminum latent heat storage system for the fluoride-salt-cooled high-temperature reactor (opens in a new tab)

  7. Tritium transport, corrosion, and Fuel performance modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR)

    The Fluoride Salt-Cooled High-Temperature Reactor (FHR) is a pebble bed nuclear reactor concept fueled by tristructural isotropic (TRISO) fuel particles embedded in graphite spheres and cooled by a liquid fluoride salt known as "flibe" (7LiF-BeF2). A system of models was developed which enabled …

    mit Repository record for Tritium transport, corrosion, and Fuel performance modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR) (opens in a new tab)

  8. Tritium production analysis and management strategies for a Fluoride-salt-cooled high-temperature test reactor (FHTR)

    The Fluoride-salt-cooled High-temperature Test Reactor (FHTR) is a test reactor concept that aims to demonstrate the neutronics, thermal-hydraulics, materials, tritium management, and to address other reactor operational and maintenance issues before a commercial Fluoride-salt-cooled …

    mit Repository record for Tritium production analysis and management strategies for a Fluoride-salt-cooled high-temperature test reactor (FHTR) (opens in a new tab)

  9. Managing tritium inventory and release with carbon materials in a fluoride salt-cooled high-temperature reactor

    The Fluoride Salt-Cooled High-Temperature Reactor (FHR) is an advanced reactor concept, that uses molten-salt coolant and solid-uranium fuel composed of graphite and silicon carbide-encapsulated tri-structural isotropic (TRISO) particles. The primary coolant salt is known as flibe (7Li2BeF4), which …

    mit Repository record for Managing tritium inventory and release with carbon materials in a fluoride salt-cooled high-temperature reactor (opens in a new tab)

  10. Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR)

    … in designing the decay heat removal system for a Fluoride salt-cooled High-temperature Reactor (FHR). The loop of interest operates with a single phase, near ambient pressure molten salt coolant. Most of the codes used for LWR safety and licensing were designed to model more complex heat transfer …

    unm Repository record for Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR) (opens in a new tab)

  11. Investigation and design of a secure, transportable fluoride-salt-cooled high-temperature reactor (TFHR) for isolated locations

    … a preliminary design for a transportable fluoride salt cooled high temperature reactor (TFHR) intended for use as a variable output heat and electricity source for off-grid locations. The goals of the project were to design an economic reactor: a) Sized for the average load of a site but …

    mit Repository record for Investigation and design of a secure, transportable fluoride-salt-cooled high-temperature reactor (TFHR) for isolated locations (opens in a new tab)

  12. Preventing fuel failure for a beyond design basis accident in a fluoride salt cooled high temperature reactor

    The fluoride salt-cooled high-temperature reactor (FHR) combines high-temperature coated-particle fuel with a high-temperature salt coolant for a reactor with unique market and safety characteristics. This combination can eliminate large-scale radionuclide releases by avoiding major fuel failure …

    mit Repository record for Preventing fuel failure for a beyond design basis accident in a fluoride salt cooled high temperature reactor (opens in a new tab)

  13. Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor

    … use a lithium- or beryllium-bearing primary salt coolant will require technical solutions to mitigate the environmental release of tritium. One such design is the Fluoride-Salt-Cooled High-Temperature Reactor (FHR), which combines a molten Flibe (2LiF-BeF₂) salt coolant and tri-structural …

    mit Repository record for Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor (opens in a new tab)

  14. The influence of surface tension on F2-Bubble Morphology at detachment from carbon electrodes in KF-2HF molten fluoride salt

    … on amorphous carbon electrodes in KF-2HF molten salt to study the effect of surface tension (ϒ) on the profile of a bubble. F2 is used for the purification and enrichment of fuel in the nuclear industry. Its generation is energy-intensive because of electrical resistances caused by the adhesion …

    uoit Repository record for The influence of surface tension on F2-Bubble Morphology at detachment from carbon electrodes in KF-2HF molten fluoride salt (opens in a new tab)

  15. Design optimization and analysis of a fluoride salt cooled high temperature test reactor for accelerated fuels and materials testing and nonproliferation and safeguards evaluations

    Fluoride Salt Cooled High Temperature Reactors (FHRs) are a new reactor concept that have recently garnered interest because of their potential to serve missions and generate revenue from sources beyond those of traditional base-load light water reactor (LWR) designs. This potential is facilitated …

    mit Repository record for Design optimization and analysis of a fluoride salt cooled high temperature test reactor for accelerated fuels and materials testing and nonproliferation and safeguards evaluations (opens in a new tab)

  16. FLOW VISUALIZATION OF TWO-PHASE FLOW IN MOLTEN-SALT: HELIUM BUBBLING IN LITHIUM FLUORIDE - SODIUM FLUORIDE - POTASSIUM FLUORIDE (LIF- NAF- KF)

    … flow visualization experiments in molten salt. A stainless-steel 316 (SST316) test apparatus equipped with a clear quartz section was designed to conduct visualization experiments of single helium bubbles rising in fluoride salt within a temperature range of 460 – 650 °C. The fluoride-salt

    tamu Repository record for FLOW VISUALIZATION OF TWO-PHASE FLOW IN MOLTEN-SALT: HELIUM BUBBLING IN LITHIUM FLUORIDE - SODIUM FLUORIDE - POTASSIUM FLUORIDE (LIF- NAF- KF) (opens in a new tab)

  17. Advancing radiative heat transfer modeling in high-temperature liquid-salts

    … the use of high Prandtl number liquid-salts in energy generation systems, including fluoride salt-cooled high-temperature reactors (FHRs), molten salt reactors (MSRs), fusion devices, and concentrated solar power plants. The temperature distribution in the coolant salts can be affected …

    mit Repository record for Advancing radiative heat transfer modeling in high-temperature liquid-salts (opens in a new tab)

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

    … while phasing out fossil fuels. Research on the fluoride salt cooled high temperature reactor (FHR), which is funded by the United States Department of Energy (DOE), has developed smoothly with the ultimate goal of a 2030 deployment. One challenge presented by FHR is that the primary coolant salt

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

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

    … 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 properties, which …

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

  20. On-line refueling for the advanced high temperature reactor

    … around the world are developing the Fluoride salt-cooled High-temperature Reactor (FHR) technology, due to its safety features and potential to generate high temperature energy for electricity and process heat applications. The Advanced High Temperature Reactor (AHTR) being considered …

    gatech Repository record for On-line refueling for the advanced high temperature reactor (opens in a new tab)

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