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Showing 1 to 18 of 18 for “"FLiBe"”.
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Feasibility Study of a Natural Uranium Neutron Spallation Target using FLiBe as a Coolant
… Fluoride-Beryllium Fluoride (LiF-BeF2) or FLiBe as a coolant with a natural uranium neutron spallation source applied to an accelerator driven sub-critical molten salt reactor. The study utilized two different software tools, MCNPX 2.6 and FLUENT 12.1. MCNPX was used to determine the …
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Tritium thermal desorption testing of nuclear graphites irradiated at fluoride-salt-cooled high-temperature reactor conditions
… isotropic (TRISO) coated particle fuel, molten flibe salt (LiF-BeF2) coolant, and an Air-Brayton power cycle. A prominent technical challenge for the FHR is maintaining the release of tritium generated from neutron irradiation of flibe below acceptable levels. One proposed method for …
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Tritium transport, corrosion, and Fuel performance modeling in the Fluoride Salt-Cooled High-Temperature Reactor (FHR)
… and cooled by a liquid fluoride salt known as "flibe" (7LiF-BeF2). A system of models was developed which enabled analyses of the performance of a prototypical pebble bed FHR (PB-FHR) with respect to tritium production and transport, corrosion, TRISO fuel performance, and materials stability …
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Design Space Exploration for Salt Cooled Reactor Systems
… 3) plate 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 …
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Simulation of Irradiation of a Molten Salt Loop at the MIT Reactor
… for use in MSRs. The salts considered are FLiBe, LiF-BeF₂-ZrF₄-UF₄ used in the MSRE, LiF-BeF₂-UF₄ suggested as a fuel salt by Terrestrial Energy and Flibe Energy, LiF-BeF₂-ThF₄ suggested as a blanket salt by Flibe Energy, and NaCl-UCl₃ suggested as a fuel salt by TerraPower. FLiBe will …
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Tritium retention in nuclear graphite, system-level transport, and management strategies for the fluoride-salt-cooled high-temperature reactor
… Reactor (FHR), which combines a molten Flibe (2LiF-BeF₂) salt coolant and tri-structural isotropic coated-particle fuel to produce power or process heat. Compared to current water-cooled reactors, managing tritium release from a FHR is further complicated by the mobility of tritium at …
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Tritium production analysis and management strategies for a Fluoride-salt-cooled high-temperature test reactor (FHTR)
… design for a 100 MW FHTR that uses enriched- 7Li flibe (Li2BeF4), has both thermal and fast flux testing positions for fuel and materials testing, and provides a neutron flux greater than 3E14 n/cm2 -s for accelerated irradiation testing. One of the key technical issues of the FHR and FHTR is …
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Initiating Event Analysis of a Lithium Fluoride Thorium Reactor
… thesis will study the LFTR design proposed by Flibe Energy. An October 2015 Electric Power Research Institute report on the Flibe Energy LFTR asked “what-if?” questions of subject matter experts and compiled a list of key hazards with the most significant consequences to the safety or integrity …
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Fluoride-salt-cooled high-temperature test reactor thermal-hydraulic licensing and uncertainty propagation analysis
… prismatic core design; two candidate coolants, flibe (LiF-BeF2) and nafzirf (NaF-ZrF4); and forced flow and natural circulation conditions to compare operating regions and LSSS power (maximum power not exceeding any thermal limits). The calculated operating region accounts for uncertainty (2 …
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HYPERION: A HYdrogen PERmeatION Experiment to Quantify Hydrogen Transport in Fusion-Relevant Molten Salts
… transport properties of molten salts like FLiBe is crucial for the development of advanced nuclear technologies like lithium-bearing liquid immersion breeding blankets for fusion reactors. Tritium production and the quantification of its mobility in these materials is necessary for …
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Accelerated atomistic prediction of structure, dynamics and material properties in molten salts
… KF, NaF, BeF2, LiCl, KCl, NaCl, 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 …
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Fail-safe source-driven fission and fusion-fission hybrid reactor configurations
… surrounded by a reflector. A 232Th and 233U FLiBe molten salt wasused as the fuel in the core. The reactor is made criticalwith the addition of a thin region of FLiBe salt with a spike of fissile material (233U). With a kin the core and total system effkof unity, the flux profile for the …
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On-line refueling for the advanced high temperature reactor
… as moderator, TRISO particles as fuel and FLiBe as coolant. The AHTR reference design is based on a traditional batch refueling approach, which requires to shut down the reactor and replace/reshuffle a certain amount of fuel assemblies in the core at a specific frequency. Several options …
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Impact of thorium based molten salt reactor on the closure of the nuclear fuel cycle
… a mixed carrier salt of lithium and beryllium (FLiBe). The objective of this research was to complete feasibility studies of a small commercial thermal LFTR. The focus was on neutronic calculations in order to prescribe core design parameter such as core size, fuel block pitch (p), fuel channel …
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Managing tritium inventory and release with carbon materials in a fluoride salt-cooled high-temperature reactor
… particles. The primary coolant salt is known as flibe (7Li2BeF4), which was chosen for its desirable thermal-hydraulic and neutronic properties. Under irradiation, coolant salts containing lithium capture neutrons generating tritium in quantities that are several orders of magnitude larger than …
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The effect of ICRF and LHCD waveguide and launcher location on tritium breeding ratio and radiation damage in fusion reactors
… materials were chosen: two liquid blankets (FliBe and Pb-17Li) and two solid blankets (Li4SiO4 and Li2TiO3). This was to test whether or not blanket material affects the optimal location of the launchers. We find that from the neutronics point of view the overall optimal location is the …
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Scaling Analysis for the Direct Reactor Auxiliary Cooling System for AHTRs
… power, i.e., the decay power being 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 …
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Species Chemistry and Electrochemical Separation in Molten Fluoride Salt
… 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 molten FLiNaK salt to achieve its separations, and provide fundamental properties to instruct the …