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Search theses and dissertations gathered from participating repositories worldwide. Every result links back to the library that holds it. No account is needed.
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Showing 1 to 20 of 23 for “"first wall"”.
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An Analytical Model for Fusion First-Wall Temperature Calculations (Conduction)
… calculation of temperatures in fusion reactor first walls. The model utilizes input quantities based on plasma physics calculations and couples a two-and-one-half-dimensional geometric analysis with a one-dimensional heat conduction analysis in determining temperature profiles over the surface …
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Design and Engineering of Advanced Fuel Fusion Reactor First Wall Systems
Made available in DSpace on 2017-07-06T18:55:42Z (GMT). No. of bitstreams: 2 Olson_Richard_E_MS.pdf: 36443626 bytes, checksum: 495d7b0e83529c3ec6c15310fe3ee2d7 (MD5) license.txt: 4813 bytes, checksum: 715c4321821a960fa1a1e91d2ac7ebce (MD5) Previous issue date: 1979
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Kinetic Study of the Sheath Region Near the First Wall for Tokamak Fusion Reactors
Made available in DSpace on 2017-07-06T18:56:15Z (GMT). No. of bitstreams: 3 Schwager_Lou_Ann_MS.pdf: 30433195 bytes, checksum: 4e568494b260d6c2295e0c3c8e5c9c60 (MD5) Schwager_Lou_Ann_MS_ABS.pdf: 341201 bytes, checksum: a7aa856d8326e24ad6c22a381e5dafd2 (MD5) license.txt: 4813 bytes, checksum: …
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Thermal transient computation for a CTR blanket following a major plasma disruption
… a neutronic and transient thermal study of the first wall and blanket region of a typical controlled thermonuclear reactor (CTR). Previous studies assumed a neutron wall loading of 1 ~ 5 MW/m², and usually an infinite slab for a blanket region in calculating the transient thermal behavior …
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Real-time RBS analysis of plasma erosion in DIONISOS
… directly surrounding the plasma, known as the first wall, will be in contact with a cooler plasma, closer to 5 eV, and must be able to withstand intense neutron radiation as well as high heat fluxes. It is still unclear how some proposed first wall materials such as tungsten and molybdenum will …
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Fusion-Product Transport in Axisymmetric Tokamaks: Losses and Thermalization
… angle and local angle-of-incidence at the first wall. The flux is strongly peaked at near grazing incidence, suggesting that blistering-injected impurities can reduce reactor burn times by 50-70%. Non-prompt losses (during slowing down, without anomalous effects) are also calculated to be …
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Moderation of high-energy fast neutrons in beryllium from a tokamak fusion reactor and heat transfer to the cooling water system
… MC software of a simplified model of the ITER first wall and blanket. Energy deposited in regions of the model using FLUKA are used to calculate a polynomial heat flux profile through the model. One dimensional conductive heat transfer through the model is performed and the cooling capacity of …
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Study of molybdenum sources and screening in the Alcator C-Mod tokamak
… of molybdenum, a high Z material, as a tokamak first wall surface. Understanding the molybdenum production mechanism is crucial if one wants to minimize it. A simple physical sputtering model has been developed that calculates the molybdenum source at the divertor, providing satisfactory …
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Investigation of Alfvén eigenmodes in Alcator C-Mod using active MHD spectroscopy
… to incomplete thermalization and possible first wall damage. These consequences must be avoided in next step burning plasma devices and thus an investigation into the stability of TAE's in present machines un- der reactor-like conditions is essential. Measurement of the damping rate of …
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Messung und Analyse von neutroneninduzierten Aktivitäten in Materialien zukünftiger Kernfusionsreaktoren
… steels, which are candidate materials for the first wall and blanket structure of. The characteristic feature of ODS steels is to introduce Y2O3 oxide particles into structural materials like EUROFER to improve the high-temperature strength and to maintain superior radiation resistance. CuCrZr …
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Studies of Edge Fluctuations of Negative Triangularity Plasma on TCV using a New Gas-Puff Imaging Diagnostic
… with the exhaust heat and particle loads on the wall materials. Edge plasma turbulence differs depending on various plasma conditions including plasma shape, e.g., the triangularity (δ). Negative δ is of great interest, as it is known to exhibit a substantial increase in con-finement compared to …
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Interaction of plasmas with lithium and tungsten fusion plasma facing components
… is the interaction of the fusion plasma with the first wall of the 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, …
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Technology and engineering of liquid lithium for fusion applications
… the interaction of the fusion plasma with the first wall of the device, particularly in the divertor of the tokamak. Edge cooling, impurity generation, and first wall erosion among others all have root causes that lie in particle and energy exchanges that occur at the plasma boundary. Solid …
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Investigation of sub-meter shields for a low aspect ratio D-T Tokamak fusion reactor
… a magnesium borohydride blanket with a tungsten first wall. The resulting nuclear heating density for a 100MW, R=1m D-T tokamak employing 0.1 - 0.2m shields is shown to have the potential to threaten the ability of such a device to sustain net electricity.
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Tokamak burn phase energy optimization with volumetric and wall interaction effects
… ion buildup through the use of a particle-wall interaction model. The D-D, D-T, D-³He reactions are all considered in this model. The energy carried off by the neutrons in the D-D and D-T reactions is lost from the plasma. Impurities enter the plasma as a result of wall interactions with …
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Forward Modeling for Bolometry and Disruption Mitigation in Tokamaks or How to Kill Your Plasma With Confidence, Style, and Pizzazz
… radiate energy out of the plasma and onto the first wall. Evenly distributed radiation causes less damage than unmitigated disruption pathways, which deliver concentrated heat loads. In order to successfully develop and deploy mitigation systems, it is important to accurately measure and …
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Effects of suprathermal fusion particles in tokamak plasmas
… When used to determine 3.52-MeV alpha particle-wall-loadings, code RIPALF, which is based on this probability function, predicts the position of local ""hot spots"" along the first wall. Either of the codes, SYMALF or RIPALF, can be used to calculate the net spatial charge build-up arising from …
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Radiation asymmetry and MHD activity in rapid shutdowns on Alcator C-Mod
… have the potential to cause severe material wall damage to large tokamaks like ITER.e mitigation of disruption damage is an essential part of any fusion reactor system. Massive gas injection (MGI) rapid shutdown is a technique in which large amounts of noble gas are injected into the plasma …
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Runaway Electron termination dynamics in fusion plasmas
L'abstract è presente nell'allegato / the abstract is in the attachment
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