Neste trabalho foram estudadas algumas propriedades de transporte de sistemas dinâmicos caóticos descritos por mapas. O trabalho tem seu foco principal em plasmas de fusão gerados em reatores denominados tokamaks. Primeiramente foi estudado o transporte de linhas de campo magnético em plasmas de cisalhamento reverso perturbado por um Limitador Magnético Ergódico (LME) em tokamaks de seção transversão circular. A deposição de linhas de campo magnético é caracterizada por padrões de estruturas denominados ``footprints';'; magnéticos. Os "footprints';'; surgem devido aos vestígios deixados pela sela caótica das linhas de campo. Para os intervalos de fator de segurança estudados, estes efeitos na parede da câmara estão associados com o grudamento de linhas de campo e canais de escape devido a cadeias de ilhas internas próximas à última superfície de fluxo não-destruída. Neste trabalho também exploramos um método de construção de um mapa integrável simplético bidimensional, associado a um sistema hamiltoniano, dado um conjunto de pontos fixos e curvas invariantes. O método foi utilizado para encontrar o mapa de Poincaré não-perturbado para linhas de campo em tokamaks de alta razão de aspecto com um desviador poloidal. O mapa integrável foi então perturbado por uma perturbação impulsiva que descreve uma ressonância assimétrica na borda do plasma. O mapa perturbado não-integrável é aplicado para estudar a estrutura de linhas de campo magnético abertas na região entre o plasma e a parede da câmara. Com isto foram reproduzidos os principais aspectos de transporte obtidos por integração numérica das equações de linhas de campo magnético, tais como: comprimentos de conexão e "footprints';'; magnéticos na placa do desviador. Otimizamos o mapa encontrado através deste método introduzindo um potencial formado por seis parábolas unidas suavemente dispostas a formar um potencial com dois pontos de mínimo. Com isto o mapa resultante se mostrou mais versátil e capaz de reproduzir superfícies com topologias bastante particulares. Outro modelo desenvolvido neste trabalho reproduz superfícies magnéticas de tokamaks munidos de desviadores, com escolhas específicas de: posição do ponto de X, triangularidade, elongação e eixo magnético. O modelo é composto por um conjunto de condutores infinitos paralelos conduzindo corrente elétrica. Utilizamos cinco condutores para reproduzir a topologia das superfícies magnéticas similares ao do International Thermonuclear Experimental Reactor (ITER). Com isto estudamos algumas propriedades da camada estocástica formada próximo à separatriz.

This thesis comprises of essentially two parts. The first deals with materials in a fusion reactor and examines how neutron damage affects material in a fusion reactor, with focus on how this is important for plasma damage. The methods used are neutron transport, primary event analysis and molecular dynamics. It found that the neutron damage by 14 MeV neutrons is restricted to back scatter events within the surface (first 20 microns). Molecular dynamics analysis showed that the issue of cascades is heavily dependent on direction of primary event and the energy of such. Statistical analysis was done to provide a standard approach for modelling of damage through neutrons. The second deals with the relaxation of magnetic flux ropes with an emphasis on kink unstable flux ropes. A relaxation model was developed which shows good approximation to simulation results of merging magnetic flux ropes. Subsequently, work was done to establish the physical processes involved in relaxation. This was done by examining magnetohydrodynamic (MHD) simulations of two flux ropes, one unstable and one stable. It was found that there is is a clear distance at which merger does not occur any more. Furthermore, a critical current seems to be a requirement at the edge a stable flux rope.

This work revolves around the use of fractional order calculus in control science. Techniques such as fractional order universal adaptive stabilization (FO-UAS), and the fascinating results of their application to real-world systems, are presented initially. A major portion of this work deals with fractional order modeling and control of real-life systems like heat flow, fan and plate, and coupled tank systems. The fractional order models and controllers are not only simulated, they are also emulated using analog hardware. The main aim of all the above experimentation is to develop a fractional order controller for plasma position control of the Saskatchewan torus-1, modified (STOR-1M) tokamak at the Utah State University (USU) campus. A new method for plasma position estimation has been formulated. The results of hardware emulation of plasma position and its control are also presented. This work performs a small scale test measuring controller performance, so that it serves as a platform for future research efforts leading to real-life implementation of a plasma position controller for the tokamak.

Les scénarios avancés, développés depuis moins d'une dizaine d'année avec la découverte des barrières internes de transport et la maîtrise du profil de courant, insufflent un nouvel élan au tokamak en direction d'un futur réacteur à fusion thermonucléaire contrôlée. Le Joint European Torus (JET) installé au Royaume-Uni, est actuellement le dispositif expérimental le plus performant au monde en terme de puissance fusion. Il a permis d'acquérir une riche expertise sur ces régimes à confinement amélioré. La réduction du transport turbulent, désormais indissociable de l'optimisation de la forme du profil de courant - obtenue par exemple avec l'onde hybride ou le courant autogénéré de bootstrap, peut être caractérisée simplement à l'aide d'un critère qui donne accès à la plupart des informations utiles concernant les barrières . Ses deux principaux domaines d'utilisation sont l'analyse des bases de données et les applications temps réel. Les modèles de transport dits de courbe en « S » exhibent des propriétés intéressantes que conforte l'expérience, tandis que les dépendances non-linéaires et multivariables de la diffusivité thermique du plasma peuvent être approchées grâce à un réseau de neurones, suggérant un nouveau moyen d'investigation et de modélisation du transport. Enfin, les toutes premières démonstrations expérimentales de contrôle en temps réel des barrières internes de transport et du profil de courant ont été réalisées sur JET, ouvrant la voie à des systèmes d'asservissement sophistiqués.

While magnetohydrodynamic (MHD) instabilities are considered one of the intriguing topics in tokamak physics, a feasibility study was conducted in the Saskatchewan Torus-Modified (STOR-M) tokamak to investigate the global MHD activities during the normal (L-mode) and improved (H-mode) confinement regimes. The experimental setup consists of 32 discrete Mirnov coils arranged into four poloidal arrays and mounted on STOR-M at even toroidal distances. The perturbed magnetic field fluctuations during STOR-M discharges were acquired and processed by the Fourier transform (FT), the wavelet analysis and the singular value decomposition (SVD) techniques. In L-mode discharges, the poloidal MHD mode numbers varied from 2 to 4 with peak frequencies in the range 20-40 kHz. The dominant toroidal modes were reported between 1 and 2 oscillating at frequencies 15-35 kHz. In another experiment, a noticeable MHD suppression was observed during the H-mode-like phase induced by the compact torus (CT) injection into STOR-M. However, a burst-like mode called the gong mode was triggered prior to the H-L transition, followed by coherent Mirnov oscillations. Mirnov oscillations with strong amplitude modulations were observed in the STOR-M tokamak. Correlations between Mirnov signals and soft x-ray (SXR) signals were found.

Resonant Magnetic Perturbation (RMP) fields produced by external control coils are considered a viable option for the suppression of Edge Localized Modes (ELMs) in present and future tokamaks. Repeated reversals of the toroidal phase of the I-coil magnetic field in RMP shot 147170 on DIII-D has generated uniquely different edge pedestal profiles, implying different edge transport phenomena. The causes, trends, and implications of RMP toroidal phase reversal on edge transport is analyzed by comparing various parameters at 0 and 60 degree toroidal phases, with an I-coil mode number of n=3. An analysis of diffusive and non-diffusive transport effects of these magnetic perturbations it the plasma edge pedestal for this RMP shot is characterized by interpreting the ion and electron heat diffusivities, angular momentum transport frequencies, ion diffusion coefficients, and pinch velocities for both phases.

While magnetohydrodynamic (MHD) instabilities are considered one of the intriguing topics in tokamak physics, a feasibility study was conducted in the Saskatchewan Torus-Modified (STOR-M) tokamak to investigate the global MHD activities during the normal (L-mode) and improved (H-mode) confinement regimes. The experimental setup consists of 32 discrete Mirnov coils arranged into four poloidal arrays and mounted on STOR-M at even toroidal distances. The perturbed magnetic field fluctuations during STOR-M discharges were acquired and processed by the Fourier transform (FT), the wavelet analysis and the singular value decomposition (SVD) techniques. In L-mode discharges, the poloidal MHD mode numbers varied from 2 to 4 with peak frequencies in the range 20-40 kHz. The dominant toroidal modes were reported between 1 and 2 oscillating at frequencies 15-35 kHz. In another experiment, a noticeable MHD suppression was observed during the H-mode-like phase induced by the compact torus (CT) injection into STOR-M. However, a burst-like mode called the gong mode was triggered prior to the H-L transition, followed by coherent Mirnov oscillations. Mirnov oscillations with strong amplitude modulations were observed in the STOR-M tokamak. Correlations between Mirnov signals and soft x-ray (SXR) signals were found.

Fast magnetosonic waves in the ion cyclotron range of frequencies have the potential to heat plasma and drive current in a thermonuclear fusion reactor. A code, SELFO-light, has been developed to study the physics of ion cyclotron resonantheating and current drive in thermonuclear fusion reactors. It uses a global full wave solver LION and a new 1D Fokker-Planck solver for the self-consistent calculations of the wave field and the distribution function of ions.In present day tokamak experiments like DIII-D and JET, fast wave damping by ions at higher harmonic cyclotron frequencies is weak compared to future thermonuclear tokamak reactors like DEMO. The strong damping by deuterium, tritium and thermonuclear alpha-particles and the large Doppler width of fast alpha-particles in DEMO makes it difficult to drive the current when harmonic resonance layers of these ionspecies are located at low field side of the magnetic axis. At higher harmonic frequencies the possibility of fast wave current drive diminishes due to the overlapping of alpha-particle harmonic resonance layers. Narrow frequency bands suitable for the fast wave current drive in DEMO have been identified at lower harmonics of the alpha-particles. For these frequencies the effect of formation of high-energy tails in the distribution function of majority and minority ion species on the current drive have been studied. Some of these frequencies are found to provide efficient ion heating in the start up phase of DEMO. The spectrum where efficient current drive can be obtained is restricted due to weak electron damping at lower toroidal mode numbers and strong trapped electron damping at higher toroidal mode numbers. The width of toroidal mode spectra for which efficient current drive can be obtained have been identified, which has important implications for the antenna design. / <p>QC 20130327</p>

京都大学 / 新制・課程博士 / 博士(工学) / 甲第23883号 / 工博第4970号 / 新制||工||1776(附属図書館) / 京都大学大学院工学研究科機械理工学専攻 / (主査)教授 蓮尾 昌裕, 教授 鈴木 基史, 教授 江利口 浩二 / 学位規則第4条第1項該当 / Doctor of Philosophy (Engineering) / Kyoto University / DFAM

Title: Materials for fusion applications and their interaction with tokamak plasma Author: Veronika Klevarová Department: Department of Physics of Materials Supervisor: doc. RNDr. Miloš Janeček, CSc., Department of Physics of Materials Abstract: Tungsten represents a perspective option in the context of fusion devices first-wall materials. In the first part of this work, set of tungsten samples with variable grain size was prepared by spark plasma sintering. Specimens were exposed to steady state deuterium plasma beam and high energy heat pulses, simulating thus the normal operation in the tokamak. As a consequence of the exposure, samples surfaces were roughened, as-prepared grains were recovered and in some cases cracks were formed. Moreover, post-irradiation analysis of the damaged samples revealed activation of in-grain slip systems within the loaded surfaces. Threshold grain diameter for this mechanism was determined to be between 5.5 - 6.6 μm at the particular loading conditions. However, damaged features showed to depend more on the fabrication parameters than on the grain diameter. Synergistic effects of simultaneous loading were proven to be important since those reduced the heat propagation within the volume of the tested samples. In the second part of this thesis, introduction to plasma-surface...