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Showing 1 to 5 of 5 for “"AHTR"”.

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

    … The Advanced High Temperature Reactor (AHTR) being considered in this study is a FHR design developed at Oak Ridge National Laboratory (ORNL) and based on the use of graphite as moderator, TRISO particles as fuel and FLiBe as coolant. The AHTR reference design is based on a traditional …

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

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

    The Advanced High Temperature Reactor (AHTR) is one of the advanced rector concepts that have been proposed for Gen IV reactors. The AHTR combines four main proven nuclear technologies, namely, the liquid salt of molten salt reactors, the coated particle fuel (TRISO particle) of high-temperature …

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

  3. Comparative review of the benefits and flexibility of small modular reactor designs

    … on the light water NuScale and the gas cooled AHTR designs. In assessing the level of safety, the typical general design and safety criteria were reviewed to establish a basis to compare the NuScale and AHTR designs. The need for flexibility to support grid operators and the ability of a …

    cape-town Repository record for Comparative review of the benefits and flexibility of small modular reactor designs (opens in a new tab)

  4. Nuclear tanker producing liquid fuels from air and water

    … salt-cooled advanced high temperature reactor (AHTR) coupled to a supercritical carbon dioxide (S-CO₂) recompression cycle operating at 25.0 MPa and 670°C. This more advanced 1,456 MWth option has a 45% cycle efficiency, a 42% improvement over the PWR option. In terms of reactor power heat input …

    mit Repository record for Nuclear tanker producing liquid fuels from air and water (opens in a new tab)

  5. 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)