Thesis (Ph. D.)--University of Texas at Austin, 2001. / Vita. Includes bibliographical references. Available also from UMI/Dissertation Abstracts International.

Thesis (Ph. D.)--University of Texas at Austin, 1998. / Vita. Includes bibliographical references (leaves 155-162). Available also in a digital version from Dissertation Abstracts.

Thesis (Ph. D.)--University of Wisconsin--Madison, 1980. / Typescript. Vita. eContent provider-neutral record in process. Description based on print version record. Includes bibliographical references.

Thesis (Ph.D.) - University of St Andrews, March 2007.

Thesis (Ph. D.)--University of Texas at Austin, 1998. / Vita. Includes bibliographical references (leaves 252-257). Available also in a digital version from Dissertation Abstracts.

Thesis (Ph. D.)--University of Texas at Austin, 2004. / Supervisor: Kenneth W. Gentle. Vita. Includes bibliographical references.

Thesis (M. S.)--Nuclear and Radiological Engineering, Georgia Institute of Technology, 2006. / Dr. Cassiano de Oliveira, Committee Member ; Dr. John Mandrekas, Committee Member ; Dr. Weston M. Stacey, Committee Chair. Includes bibliographical references.

Electron Bernstein waves are a mode of oscillation in a plasma, thought a candidate for providing radiofrequency heating and non-inductive current drive in spherical tokamaks. Previous studies of these modes have relied on neglecting or simplifying the contribution made by relativistic effects. This work presents fully relativistic numerical results that show the mode's dispersion relation for a wide range of parameters. Relativistic effects are shown to shift the location of the resonance as in previous studies, but the effects beyond this are shown to matter only in high temperature (10-20keV) plasmas. At these higher temperatures however, the fully relativistic model differs markedly. The assumption that the mode is electrostatic is looked at, and found to be inadequate for describing fully the electron Bernstein modes dispersion relation. Simple estimates that neglect toroidal effects show current drive efficiency is expected to be an order of magnitude higher than that for conventional electron cyclotron current drive using the O or X modes. It is shown for a number of model tokamaks that heating the center of the plasma and driving current using EBWs is impossible launching from the outside due to strong damping of the wave at higher cyclotron harmonics. Results from a code based on a more complicated semi-analytic model of current drive, that includes toroidal effects and calculates the average current drive over the magnetic surface, confirm the higher expected current drive efficiency, and the code is shown to give good agreement with a Fokker-Planck code. The higher values of perpendicular refractive index associated with the EBWs are shown to mitigate the deleterious effects of trapping on current drive efficiency to a small extent. The details of the magnetic field are found to be unimportant to the calculation beyond determing where the wave is absorbed. The codes written to produce these results are outlined before each set of results. The last of these is considerably faster than conventional Fokker-Planck codes and a useful tool in studying electron cyclotron current drive in the future.

En el estudio de la fusión por confinamiento magnético es crucial conocer con detalle las condiciones físicas del plasma confinado. En este sentido los códigos de simulación son una herramienta muy útil para interpretar las propiedades del plasma. A lo largo de esta tesis se ha estudiado las propiedades del plasma de tokamaks y stellarators y se ha contribuido al desarrollo del código de transporte PRETOR, creado en el JET. Estos estudios se han realizado dentro de la colaboración existente entre el DFEN de la UPC y el Laboratorio Nacional de Fusión del CIEMAT.El código PRETOR permite simular la variación radial y la evolución temporal de las principales magnitudes físicas de un plasma de fusión. Para valorar la bondad de los modelos implementados en el código y determinar la corrección de sus resultados los resultados de la simulación de las magnitudes más relevantes de diversas descargas se comparan con los datos experimentales. De esta comparación se deduce que las magnitudes simuladas presentan un buen acuerdo con los datos experimentales aunque debe destacarse que los errores experimentales son bastante grandes y no siempre están disponibles.En el desarrollo de esta tesis también se ha aplicado el código PRETOR para el estudio de la parada de emergencia de ITER-DDR, con 1500 MW de potencia de fusión funcionando en un estado estacionario en ignición. Se ha estudiado con detalle la evolución del plasma durante una parada implementada mediante la interrupción del suministro de combustible. Este método se muestra efectivo para reducir la potencia de fusión en unas decenas de segundos evitando una disrupción del plasma en todo el escenario.Se han realizado diversas modificaciones en el código para hacerlo más versátil y adaptarlo a las necesidades específicas que han ido surgiendo. La modificación más destacada es la incorporación a PRETOR de una rutina más elaborada que la inicialmente implementada en el código para el cálculo de la deposición de potencia adicional por inyección de haces neutros.En los últimos años la investigación de stellarators ha adquirido una creciente importancia debido a las ventajas que presentan este tipo de dispositivos. Además hay que destacar que el programa de fusión por confinamiento magnético español se centra en el Heliac Flexible TJ-II de la asociación EURATOM-CIEMAT. Por estos motivos y para disponer de un código que sea capaz de simular descargas de stellarators, PRETOR ha sido modificado de forma substancial para crear la versión PRETOR-Stellarator. Esta modificación del código presenta un aspecto inédito de la tesis en el ámbito internacional.Los módulos que han sido adaptados afectan a la configuración magnética, al transporte de energía y partículas y a la geometría del plasma. Una vez modificado el código, éste se ha aplicado al análisis del plasma de Heliac Flexible TJ-II. El objetivo de este estudio es comprobar que las modificaciones introducidas en PRETOR permiten simular correctamente descargas de stellarators. Los resultados obtenidos con PRETOR se comparan con los obtenidos con el código PROCTR, un código utilizado en el CIEMAT para el estudio del TJ-II y de otros stellarators.Los resultados demuestran que los perfiles de temperatura se reproducen correctamente, estos resultados son similares a los obtenidos con PROCTR. Los valores experimentales de la potencia radiada y de la energía almacenada en el plasma han sido satisfactoriamente predichos mediante la simulación de PRETOR-Stellarator.El camino abierto por esta tesis permitirá ahondar en el estudio del plasma del heliac flexible TJ-II, el código está disponible para utilizarse en este dispositivo e incorporar nuevas modificaciones para adaptarlo a las necesidades que vayan apareciendo. / In the study of the fusion by magnetic confinement it is crucial to know the physical behaviour of the confined plasma with detail. In this sense the simulation codes are a very useful tool to analyse the properties of the plasma. Throughout this thesis the properties of the plasma of tokamaks and stellarators has been studied and the transport code PRETOR, created in the JET, has been developed. These studies have been developed within the existing collaboration between the DFEN in the UPC and the Laboratorio Nacional de Fusión of the CIEMAT.The PRETOR code allows the simulation of the radial variation and the temporal evolution of the main physical magnitudes of a fusion plasma. The results of the simulation of the most important magnitudes of diverse shots are compared with the experimental data in order to evaluate the goodness of the models implemented in the code and to determine the correction of their results. From this comparison it's deduced that the simulated magnitudes present a good agreement with the experimental data although it must be stand out that the experimental errors are quite large and they not always are available.In the development of this thesis the code PRETOR has also been applied to the study of the shutdown emergency of ITER-DDR, with 1500 MW of fusion power operating in an ignition stationary state. The evolution of the plasma has studied with detail during the shutdown implemented by means of the interruption of the fuel injection. This method is effective to reduce the fusion power in tens of seconds avoiding a plasma disrupción in all the scenarios. Several modifications have been made in the code in order to make it more versatile and to adapt it to the specific arisen necessities. The most outstanding modification is the incorporation to PRETOR of more complex routine than that initially implemented in the code for the calculation of the additional power deposition by neutral beam injection.In the last years the investigation of stellarators has acquired an increasing importance due to the advantages that this type of devices presents. Besides it is necessary to emphasise that the Spanish program of fusion by magnetic confinement is focused in Flexible Heliac TJ-II in the asociación EURATOM-CIEMAT. For these reasons and in order to have a code able to simulate stellarators shots, PRETOR has been modified of substantial form to create the PRETOR-Stellarator version. This modification of the code presents an new aspect of the thesis in the international scope.The modules that have been adapted affect to the magnetic configuration, the transport of energy and particles and to the plasma geometry. Once the code has been modified, it has been applied to the analysis of TJ-II Flexible Heliac plasmas. The objective of this study is to verify that the modifications introduced in PRETOR allow to simulate correctly stellarators discharges. The results obtained with PRETOR are compared with that ones obtained with PROCTR code, a code used in the CIEMAT for the study of the TJ-II and others stellarators.The results demonstrate that the temperature profiles are reproduced correctly, these results are similar to the obtained ones with PROCTR. The experimental values of the radiated power and the stored energy in the plasma have been predicted satisfactorily by means of the simulation with PRETOR-Stellarator.The way open by this thesis will allow studying in depth the plasma of TJ-II flexible heliac, the code is available to be used in this device and to incorporate new modifications to adapt it to the necessities that will appear.