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Showing 1 to 20 of 60 for “"divertor"”.
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Modeling of Boundary Transport and Divertor Target Heat Flux - Implications for Advanced Divertor Concepts
… Simulations of C-Mod had a much shorter outer divertor leg compared to SPARC, making it difficult to use detachment studies in C-Mod to speculate on detachment in SPARC. Finally, there was only a rough idea of edge plasma conditions in SPARC, and it was not known whether detachment would even …
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Experimental classification of divertor detachment
Avoiding damage of the divertor material by keeping the power load below a certain threshold is a major challenge for the operation of future fusion devices such as ITER. For Tungsten, the foreseen ITER divertor target material, the power load must be kept below 5 MW m^2 in continuous operation. …
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Neutral Particle Modeling in the Iter Divertor
Made available in DSpace on 2017-07-06T18:48:26Z (GMT). No. of bitstreams: 3 Hayden_Douglas_B_MS.pdf: 46473420 bytes, checksum: c33f82add668f6762ac392c2ed9f138e (MD5) Hayden_Douglas_B_MS_ABS.pdf: 541488 bytes, checksum: 553a593921e5f239adda08977c01c41b (MD5) license.txt: 4813 bytes, checksum: …
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Performance of armor materials for the ITER divertor
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1996.
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Probabilistic analysis of divertor plate lifetime in tokamak reactors
Thesis (M.S.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1994.
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A bundle Divertor Design for an Advanced Fuel tokamak Reactor
Made available in DSpace on 2017-07-06T18:55:43Z (GMT). No. of bitstreams: 2 Otten_Gillis_R_MS.pdf: 24113090 bytes, checksum: d3054c68e311e2633e26793a75b6fc06 (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1976
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Transport Properties of Divertor Edge Plasmas Measured with Multi-Spectral Imaging
… create 2D poloidal maps of Tₑ and nₑ in the TCV divertor. These are the first plasma boundary measurements to provide continuous 2D coverage of Tₑ and nₑ for arbitrary magnetic geometries. These measurements were validated against co-local Thomson scattering measurements in diverted plasmas. …
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Quantification of Chemical Erosion in the Divertor of the DIII-D Tokamak
… designed to use graphite targets in the divertor for power handling and impurity control. Understanding and quantifying chemical sputtering is therefore key to the success of fusion as a clean energy source. The principal goal of this thesis is to design and carry out experiments, then …
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Effect of Coil Layout on the Performance of the Proton Divertor Collimator Device
Made available in DSpace on 2017-07-06T18:55:38Z (GMT). No. of bitstreams: 3 Nieto-Perez_Martin_De_Jesus_MS.pdf: 37147999 bytes, checksum: bbfc2369a7fa2a773876b62e67116abd (MD5) Nieto-Perez_Martin_De_Jesus_MS_ABS.pdf: 449263 bytes, checksum: dd277725702ca739ac2af2da2e808776 (MD5) license.txt: 4813 …
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Measurements of divertor target plate conditions and their relationship to scrape-off layer transport
… SOL profiles, main-chamber recycling fluxes, and divertor operation. However, questions remain about the extent to which divertor target conditions play a role in setting transport levels. The Alcator C-Mod SOL is well diagnosed and extensively characterized, making it an ideal platform to assess …
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Optimization of the thermal-hydraulic performance of the helium-cooled modular divertor with multiple jets
The divertor is a key plasma-facing component of future commercial magnetic fusion energy (MFE) reactors that helps sustain fusion reactions by removing helium ash particles and impurities from the core plasma. The divertor target plates are therefore subject to high steady-state incident heat …
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Interaction of plasmas with lithium and tungsten fusion plasma facing components
… device; an interaction which is strongest in the divertor region. Erosion, melting, sputtering, and deformation are all concerns which inform choices of divertor material. Of the many materials proposed for use in the divertor, only a few remain as promising choices. Tungsten has been chosen as …
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Characterisation of Detached Plasmas on the MAST Tokamak
… heat loading to plasma-facing components in the divertor structures is an essential prerequisite for the operation of next-generation conventional and tight aspect-ratio Tokamaks. Currently, the most attractive means of reducing this heat loading is the so-called “detached” regime, which is the …
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Study of molybdenum sources and screening in the Alcator C-Mod tokamak
… that calculates the molybdenum source at the divertor, providing satisfactory agreement with the spectroscopic results. The effect of deuterons, boron ions, and redeposited molybdenum incident on the target is included in the calculation which shows that the boron ions dominate the sputtering. …
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Enabling the simulation of helium transport in lithium for fusion devices
… Tungsten is a material being considered for the divertor component of the tokamak. However, tungsten will still receive surface damagefrom hydrogen and helium ions. Using flowing lithium to shield the tungsten divertor may reduce the surface damage to the solid divertor. Lithium also has a …
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Tokamak burn phase energy optimization with volumetric and wall interaction effects
… controlled by incorporating a charged particle divertor. A dynamic model of the burn cycle of a Tokamak is used to investigate the ion densities, temperatures and the plasma volume as a function of time. The total energy output per cycle is investigated as a function plasma current, and divertor …
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Study of ergodic divertor edge density regimes on the tokamaks Tore Supra and TEXTOR, and sensitivity of tunnel probe electron temperature measurements to a suprathermal electron component
… that is addressed in this thesis, is the ergodic divertor (ED) configuration. An ED achieves the transition between the confined plasma and the wall in a layer where the flux lines have been ergodized by a proper resonant magnetic perturbation. The connection between up- and downstream plasma …
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Heat transfer analysis of thermoelectric driven swirling flow
… problem to remove the intensive heat from the divertor region. The solid plasma facing materials (PFM) suffer from the sputtering and thermal stress. An alternative way is to utilize liquid metal especially the liquid lithium as the divertor material. An experiment on CDX-U found that a shallow …
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Study of recycling impurity retention in Alcator C-mod
… experimentally observed compression of Ar in the divertor of Alcator C-Mod. In addition it was found that under attached conditions recycling at the outer plasma edge (limiters located there) was the dominant source of Ar ions reaching the core (over 60%). For detached conditions divertor …
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