Results 1 to 10 of about 209,611 (271)
Developments on two lithium vapor-box linear test-stand experiments
Nuclear Materials and Energy, 2021 The lithium vapor-box divertor is a possible fusion power exhaust solution. It uses condensation pumping to create a gradient of vapor density in a divertor slot; this should allow a stable detachment front without active feedback.
Jacob A. Schwartz, R.J. Goldston
doaj +4 more sources
Predictive modeling of a lithium vapor box divertor in NSTX-U using SOLPS-ITER
Nuclear Materials and Energy, 2021 The unmitigated heat flux in attached operation of a fusion power plant is predicted to be destructive to any solid divertor surface. Detachment, whereby the plasma pressure drops significantly before reaching the divertor target thus greatly reducing ...
E.D. Emdee +3 more
doaj +5 more sources
The effect of gas injection location on a lithium vapor box divertor in NSTX-U
Nuclear Fusion, 2023 The lithium vapor box divertor is a proposed divertor design that will minimize contamination of the upstream plasma in a fusion device, while also ensuring protection of the target.
E.D. Emdee, R.J. Goldston
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Recent advances towards a lithium vapor box divertor
Nuclear Materials and Energy, 2017 Fusion power plants are likely to require near complete detachment of the divertor plasma from the divertor target plates, in order to have both acceptable heat flux at the target to avoid prompt damage and also acceptable plasma temperature at the ...
R.J. Goldston +4 more
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Physics design for a lithium vapor box divertor experiment on magnum PSI
Nuclear Materials and Energy, 2019 The lithium vapor box divertor is a potential solution for power exhaust in toroidal confinement devices. The divertor plasma interacts with a localized, dense cloud of lithium vapor, leading to volumetric radiation, cooling, recombination, and ...
Jacob A. Schwartz +3 more
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Comparing lithium vapor box designs in a high heat flux scenario using SOLPS-ITER
Nuclear Materials and Energy, 2023 SOLPS calculations of lithium vapor box divertor designs on NSTX-U are presented. Predictive high power simulations (Pheat=10 MW, qpeakunmitigated∼65 MW/m2) are used to compare and contrast two divertor designs.
E.D. Emdee, R.J. Goldston
doaj +4 more sources
Optimization of lithium vapor box divertor evaporator location on NSTX-U using SOLPS-ITER
Nuclear FusionCommercial fusion reactors will be faced with extremely high divertor target heat fluxes that will require mitigation. Simulations of detachment in an NSTX-U scenario projected to have 92 MW m ^−2 unmitigated peak target heat flux are presented, which ...
E.D. Emdee +3 more
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The lithium vapor box divertor
Physica Scripta, 2016 It has long been recognized that volumetric dissipation of the plasma heat flux from a fusion power system is preferable to its localized impingement on a material surface. Volumetric dissipation mitigates both the anticipated very high heat flux and intense particle-induced damage due to sputtering.
Jacob A Schwartz, Robert J Goldston
exaly +3 more sources
An out of the box vision over oxidative chemical vapor deposition of PEDOT involving sublimed iron trichloride [PDF]
Synthetic Metals, 2020 Abstract Oxidative chemical vapor deposition (oCVD) is an efficient technique to produce highly conductive films of Poly (3,4-ethylenedioxythiophene) (PEDOT). Despite numerous studies on the oCVD of PEDOT films, there is limited information on the stability of the sublimation of solid oxidants and on their impact on the polymerization reactions.
Milad Mirabedin, Brigitte Caussat
exaly +5 more sources
Nuclear FusionA promising approach to handle the intense plasma heat flux in the divertor region of a tokamak is the Vapor Box Divertor (VBD). Here plasma-lithium interaction creates a dense lithium vapor cloud which interacts with the incoming plasma, effectively ...
Fabio Romano +6 more
doaj +2 more sources