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Factors affecting the viability of a mirror type fusion reactor power plant [Master's project] NE 590 /Galbraith, D. January 1971 (has links)
Thesis--University of Michigan, 1971.
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Experimental and numerical investigation of the thermal performance of the gas-cooled divertor plate conceptGayton, Elisabeth Faye. January 2008 (has links)
Thesis (M. S.)--Nuclear Engineering, Georgia Institute of Technology, 2009. / Committee Chair: Abdel-Khalik, Said; Committee Co-Chair: Yoda, Minami; Committee Member: Ghiaasiaan, S. Mostafa. Part of the SMARTech Electronic Thesis and Dissertation Collection.
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Measurement of the internal toroidal magnetic field on the helicity injected tokamak using the transient internal probe /Galambos, James Paul. January 1996 (has links)
Thesis (Ph. D.)--University of Washington, 1996. / Vita. Includes bibliographical references (leaves 126-128).
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Plasma confinement characteristics and runaway instability in the Proto-Cleo torsatronTalmadge, Joseph Nathan. January 1982 (has links)
Thesis (Ph. D.)--University of Wisconsin--Madison, 1982. / Typescript. Vita. Description based on print version record. Includes bibliographical references (leaves 235-242).
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Fuel cycle optimization of a helium-cooled, sub-critical fast transmutation of waste reactor with a fusion neutron sourceMaddox, James Warren. January 2006 (has links)
Thesis (M. S.)--Mechanical Engineering, Georgia Institute of Technology, 2006. / Edward Hoffman, Committee Member ; Nolan Hertel, Committee Member ; Weston Stacey, Committee Chair.
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Étude de faisabilité d'un résonateur optique pour des applications aux systèmes d'injection de neutres pour la prochaine génération de réacteurs à fusion nucléaire / Feasibility study of an optical resonator for applications in neutral-beam injection systems for the next generation of nuclear fusion reactorsFiorucci, Donatella 12 June 2015 (has links)
Cette étude fait partie d'un projet plus large appelé SIPHORE (SIngle gap PHOtoneutralizer energy REcovery injector), visant à améliorer l'efficacité globale de l'un des mécanismes par lesquels le plasma est chauffe, dans un réacteur de fusion nucléaire, à savoir le système d'injection de neutres (IDN). Une composante importante d'un système IDN est le neutraliseur de faisceaux d'ions de haute énergie. SIPHORE propose de substituer le neutraliseur à cellule à gaz, utilisé dans les systèmes IDN actuels, par un photo-neutraliseur exploitant le processus de photo-détachement dans des cavités Fabry Perot. Ce mécanisme devrait permettre une efficacité globale η> 60% du système IDN, nettement plus élevée que celle actuellement possible (η <25% pour ITER). Le travail de thèse porte sur l'étude de faisabilité d'une cavité optique avec des propriétés adaptées aux systèmes IDN. Dans ce contexte, le problème de la détermination d'une conception de la cavité optique appropriée a été tout d'abord pris en considération et l'analyse théorique ainsi qu'expérimentale d'un résonateur optique ont été effectuées. Les problèmes lies aux niveaux élevés de puissance optique intracavité (~3 MW) nécessaire pour un taux de photo-neutralisation adéquat ont ensuite été prises en compte. A cet égard, nous avons traite a la fois le problème des effets thermiques sur les miroirs de la cavité en raison de leur absorption de la puissance optique intra-cavite (~1 W) et celui associe à la nécessité d'un faisceau laser d'entrée de puissance élevée (~1 kW) pour alimenter le résonateur optique. / This work is part of a larger project called SIPHORE (SIngle gap PHOtoneutralizer energy RE-covery injector), which aims to enhance the overall efficiency of one of the mechanisms through which the plasma is heated, in a nuclear fusion reactor, i.e. the Neutral Beam Injection (NBI) system. An important component of a NBI system is the neutralizer of high energetic ion beams. SIPHORE proposes to substitute the gas cell neutralizer, used in the current NBI systems, with a photo-neutralizer exploiting the photo-detachment process within Fabry Perot cavities. This mechanism should allow a relevant NBI global efficiency of η> 60%, significantly higher than the one currently possible (η<25% for ITER). The present work concerns the feasibility study of an optical cavity with suitable properties for applications in NBI systems. Within this context, the issue of the determination of an appropriated optical cavity design has been firstly considered and the theoretical and experimental analysis of a particular optical resonator has been carried on. The problems associated with the high levels of intracavity optical power (~3 MW) required for an adequate photo-neutralization rate have then been faced. In this respect, we addressed both the problem of the thermal effects on the cavity mirrors due to their absorption of intra-cavity optical power (~1W) and the one associated to the necessity of a high powerful input laser beam (~1 kW) to feed the optical resonator.
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Experimental investigation of the thermal performance of gas-cooled divertor plate conceptsHageman, Mitchell D. 04 June 2010 (has links)
Magnetic confinement fusion has the potential to provide a nearly inexhaustible source of energy. Current fusion energy research projects involve conceptual "Tokamak" reactors, inside of which contaminants are "diverted" along magnetic field lines onto collection surfaces called divertor plates. Approximately 15% of the reactor's thermal power is focused on the divertor plates, creating a need for an effective cooling mechanism. Current extrapolations suggest that divertor plates will need to withstand heat fluxes of more than 10 MW/m2. The cooling mechanism will need to use a coolant compatible with the blanket system; currently helium, and use a minimal fraction of the reactor's available pumping power; ie: will need to experience minimal pressure drops. A leading cooling concept is the Helium Cooled Flat Plate Divertor (HCFP). This thesis experimentally examines four variations of the HCFP. The objectives are to: 1. Experimentally determine the thermal performance of the HCFP with a hexagonal pin-fin array in the gap between the impinging jet and the cooled surface over a range of flow rates and incident heat fluxes; 2. Experimentally measure the pressure drop associated with the hexagonal pin-fin array over a range of flow conditions; 3. Determine and compare the thermal performance of and pressure drop associated with the HCFP for two different slot widths, 0.5 mm and 2 mm over a range of flow rates and incident heat fluxes; 4. Compare the performance of the HCFP with a hexagonal pin-fin array with that of the HCFP with a metal-foam insert and the original HCFP; 5. Provide an experimental data set which can be used to validate numerical models of the HCFP design and its variants. 6. Analytically determine the maximum heat flux which the HCFP can be expected to withstand at theoretical operating conditions in the original and pin-fin array configurations.
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Magnetic equilibria of the coaxial slow source /Smith, Roger James, January 1989 (has links)
Thesis (Ph. D.)--University of Washington, 1989. / Vita. Includes bibliographical references (leaves [136]-137).
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Dynamics and free-surface geometry of turbulent liquid sheetsDurbin, Samuel Glen, January 2005 (has links) (PDF)
Thesis (Ph. D.)--Mechanical Engineering, Georgia Institute of Technology, 2005. / Minami Yoda, Committee Co-Chair ; Said I. Abdel-Khalik, Committee Co-Chair ; S. Mostafa Ghiaasiaan, Committee Member ; Cyrus K. Aidun, Committee Member ; Donald R. Webster, Committee Member ; Ralph W. Moir, Committee Member. Includes bibliographical references.
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Model of an ablating solid hydrogen pellet in a plasmaParks, Paul B. January 1979 (has links)
Thesis--University of Illinois at Urbana-Champaign, 1977. / Includes bibliographical references (p. 126-128).
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