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Showing 1 to 20 of 36 for “"high temperature reactor"”.
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On-line refueling for the advanced high temperature reactor
… 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 in this study is a …
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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
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Air Ingress and Heat-Driven Flow Relaminarization in a Very High Temperature Reactor (VHTR)
<p>Very High Temperature Reactors (VHTRs) are one of six Generation IV reactors that have been proposed for DOE’s Next Generation Nuclear Plant. In addition to using gaseous coolants, VHTRs also display benefits of passive safety systems including intra-core natural circulation for heat removal in …
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Advanced characterizations of austenitic oxide dispersion-strengthened (ODS) steels for high-temperature reactor applications
Future advanced nuclear systems involve higher operation temperatures, intenser neutron flux, and more aggressive coolants, calling for structural materials with excellent performances in multiple aspects. Embedded with densely and dispersedly distributed oxide nanoparticles that are capable of not …
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Microstructural evolution and mechanical behavior in nickel based alloys for very high temperature reactor
Under the Gen IV advanced reactor development program, the Very High Temperature Reactor (VHTR) is the lead concept. Design and development steps are currently underway to construct a high-temperature reactor as the next generation nuclear plant (NGNP) at Idaho National Laboratory (INL). A major …
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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 …
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Evaluation of an aluminum latent heat storage system for the fluoride-salt-cooled high-temperature reactor
… medium (PCM) that transfer heat at constant temperature. The use of metallic PCMs allows LHS to be used 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. …
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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 …
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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 …
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Validation Studies of Single-Phase Natural Circulation Response of the Fluoride salt-cooled High-temperature Reactor (FHR)
… 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 problems. A single …
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Investigation and design of a secure, transportable fluoride-salt-cooled high-temperature reactor (TFHR) for isolated locations
… 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 able to increase …
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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 …
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Oxidation behavior of very high temperature reactor (VHTR) candidate materials: 316l stainless steel, Alloy 617, and Incoloy-800H
High temperature nuclear reactors require alloys to perform well at temperatures around 1000 to 1400 K. The oxidation behavior of three high temperature reactor candidate materials, 316 L stainless steel, alloy 617, and Incoloy 800-H under different conditions were investigated in the present work. …
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Effects of Thermal-Hydraulic Feedback on Burnup Modeling of the Deep Burn Modular High Temperature Reactor (DB-MHR)
Made available in DSpace on 2017-07-06T18:59:35Z (GMT). No. of bitstreams: 3 Ye_Bei_MS.pdf: 1045414 bytes, checksum: 5f391596dd3c9718291113127ba27c12 (MD5) Ye_Bei_MS_ABS.pdf: 26802 bytes, checksum: 8d516635e97ee4cb3df9cd653f65e18f (MD5) license.txt: 4813 bytes, checksum: …
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Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor
Advanced reactor concepts which 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 …
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Analysis of U-Zr-C-O Quaternary System for Applications in Advanced ZRC Coated Triso Particles
… of ZrC for use in oxide TRISO particles for Very High Temperature Reactor (VHTR) conditions to prevent kernel overpressurization and kernel migration has been proposed by several researchers. Analysis is performed incorporating first-principles thermodynamics along with out-of-pile experimental …
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Keramische Brennelemente für Kugelhaufen-Druckwasserreaktoren mit inhärenten Sicherheitseigenschaften
… and -moderated Pebble Bed Pressurized Water Reactor (PBPR) with inherent security characteristics will be presented. This concept bares analogies to the High Temperature Reactor (HTR). I will be shown, which contribution can be realized by the application of ceramic materials within this …
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Novel Synthesis and Characterization of Uranium-Zirconium Carbonitride by Direct Casting
… thermophysical properties beneficial to high temperature reactor applications such as nuclear thermal rockets. The present work investigates a novel liquid phase synthesis method involving the admission of nitrogen gas during arc melting of uranium, zirconium, and carbon. Initial …
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The Effect of Coating Parameters On Advanced TRISO Fuels With Zirconium Carbide
… conventional SiC TRISO coating system at very high temperature, not unlike the temperatures obtainable in the very high temperature reactor (VHTR) design. These problems include but are not limited to over pressurization of the kernel due to fission gas buildup as well as kernel migration, in …
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Plenum-to-plenum heat transfer characteristics under natural circulation in a scaled-down prismatic modular reactor
<p>“Gas-cooled reactor (GCR) is being developed under the Next Generation Nuclear Plant Program (NGNP) in nuclear engineering studies. As the world searches for an energy source with high energy density, clean, abundant, and storable nature to avoid global warming issues, GCR seems to be a …
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