22,375 research outputs found
Thermal profiles and improved confinement accessibility in RFX-mod and TCV
No full textHumans do not live by bread alone. Physically we are puny creatures with limited prowess, but with unlimited dreams. In the last few decades humankind reached the Moon (1969) and
built airports over the sea (1994), but 925 million people are still under- or malnourished (2010). To follow his dream to ensure every human being the same adequate quality of life, humankind needs energy. The long-term world energy scenarios (50-80 years) foresee the need for reliable, sustainable and environmental friendly sources of energy. Thermonuclear fusion is one of the main actors in the energetic basket, it offers the possibility to produce large supplies of energy at relatively low costs reducing the impact on the environment. In fact, thermonuclear fusion represents a promising chance to generate energy without the emission of carbon dioxide and the production of long living radioactive wastes. Moreover, the raw materials used as fuel in the fusion reactions, deuterium and tritium, are easily available on Earth. This chance motivates the efforts on the controlled thermonuclear fusion research. Anyway, the development of nuclear fusion as an energy source is one of the most complex scientific and technical tasks ever undertaken for non-military purposes. The nuclear fusion obtained by magnetic confinement of plasma emerged in the latest years as the most promising concept to menage the power produced by fusion reactions. The studies developed in that direction, since the fifties, yielded more and more encouraging results and important breakthroughs both in physics and technology and inspired the ITER project. This experimental reactor could give, in the next few decades, the definitive answers to many questions on the scientific and technological feasibility of a fusion reactor. One of the major concerns in magnetic confinement fusion research is the quest for the best
plasma performance, which is intimately linked to two main issues: plasma confinement and boundary conditions. Both, incidentally, are connected to plasma stability. The link between confinement and boundary conditions is very strong and found many evidences. For example in the tokamak (the magnetic confinement configuration main line) the quest for a mild plasma-wall interaction a controlled recycling led to the discovery of an ameliorated operating mode with high performance. As a matter of fact, H-mode was discovered in
ASDEX the first diverted device. In RFPs (an alternative magnetic confinement configuration) a spontaneous transition to an ameliorated plasma state, the QSH state, is due to a reduced chaos obtained with an accurate control of the magnetic boundary conditions. In turn, the access to the QSH state led to a favorable edge topology characterized by better boundary conditions. The onset of the QSH state induces an edge helical ripple which reduce the plasma wall interaction. My research activity, reported in this thesis work, focused on the accessibility conditions and characterization of improved confinement regimes in TCV tokamak and RFX-mod RFP devices. In RFX-mod my research activity focused on the study and the characterization of electron temperature profiles. Temperature is one of the key parameters that qualifies fusion plasma performance and, in RFX-mod plasmas, it is mainly determined by three quantities: plasma current, electron density and plasma magnetic state. Through a large statistical analysis the temperature profile variations were investigated and related to the main macroscopic and operational plasma parameters. This analysis resulted in scaling laws for central temperature, external temperature and temperature gradient. Some further analysis was dedicated to a distinctive feature: the appearance of transport and thermal barriers which result in better plasma performance. The formation of an Internal Transport Barrier (eITB) is triggered by the growth of a dominant MHD tearing mode which, in turn, leads to a reduced magnetic chaos
in the plasma core. Starting from previous analysis, these eITBs were investigated and their influence of the whole temperature profile addressed. Besides the established phenomena related to eITBs, the occasional appearance of extremely high gradients in the external region of the plasma column was observed. Some general observations and a first speculation on the physical mechanism leading to their formation will be presented. The work ends up in a wide and general picture which tries to clear up the physics governing the temperature profile
modifications and proposes possible operations to trigger them. Present day tokamaks high performance scenarios rely on the possibility to access the high confinement mode (H-mode). Transition from the standard confinement mode (L-mode) to the H-mode is typically achieved when the external input power exceeds a threshold. This power threshold is found to strongly depend on plasma density, toroidal magnetic field and plasma size, but many experiments have shown this power threshold to also depend on plasma shape and configuration geometry. My activity at TCV aimed at the study of such dependence, in particular the influence of X-point location on H-mode power threshold was investigated. During a two months stay in 2011, a series of experiments was dedicated to such a study. Significant variations in the power threshold due to a reduction of the X-point height has been documented, in agreement with the scaling observed in other machines. Moreover, the well-established non-monotonic density dependence of the H-mode power threshold has
been measured and recorded. In this thesis work the analysis procedure followed to the TCV experimental campaign is reported
Kinematic viscosity estimates in reversed-field pinch fusion plasmas
No full textThis paper concerns the kinematic viscosity in reversed-field pinch fusion plasmas, including both the study of numerical magneto-hydrodynamics (MHD) simulations and the analysis of RFX-mod experimental data. In the first part, we study the role of non-uniform time-constant radial viscosity profiles in 3D non-linear visco-resistive MHD simulations. The new profiles induce a moderate damp (for the velocity field) and a correspondent enhancement (for the magnetic field) of the spectral components resonating in the regions where the viscosity is higher. In the second part, we evaluate the kinematic viscosity coefficient on a wide database of RFX-mod shots according to the transport theories of Braginskii (considering parallel, perpendicular and gyro viscosity coefficients), considering the action on viscosity of ITG modes (ion temperature gradient) and according to the transport theory of Finn. We then exploit the comparison with the visco-resistive MHD simulations (where the visco-resist..
A new paradigm for RFP magnetic self-organization: results and challenges
No full textThis paper reports the most recent experimental results on quasi-single helicity (QSH) reversed field pinch (RFP) plasmas. QSH is considered a key element towards the full experimental realization of the theoretically predicted single helicity (SH) RFP. The SH RFP, where an individual resistive kink mode and its harmonics drive the dynamo electric field, is predicted to have superior confinement performance with respect to the standard multiple helicity (MH) state. Magnetic chaos is in fact strongly reduced in the SH RFP, which therefore retains all the positive features of the RFP configuration without the problems connected with the magnetic turbulence typical of the MH scenario. Data from the RFX-mod device, presented here, provide a more complete description of QSH states, indicate a positive synergy between the growth of the dominant resistive mode and the decrease in the secondary modes (with reduction of magnetic chaos and hints of confinement improvement outside the helical domain), and show a promising scaling with plasma current. Initial experiments on active control of QSH states in RFX-mod are presented
Turbulent filament properties in L and H-mode regime in the RFX-mod operating as a tokamak
No full textMagnetic order and confinement improvement in high-current regimes of RFX-mod with MHD feedback control
No full textThe RFX-mod machine (Sonato et al 2003 Fusion Eng. Des. 66 161) recently achieved, for the first time in a reversed-field pinch, high plasma current up to 1.6 MA with good confinement. Magnetic feedback control of magnetohydrodynamic instabilities was essential to reach the goal. As the current is raised, the plasma spontaneously accesses a new helical state, starting from turbulent multi-helical conditions. Together with this raise, the ratio between the dominant and the secondary mode amplitudes increases in a continuous way. This brings a significant improvement in the magnetic field topology, with the formation of helical flux surfaces in the core. As a consequence, strong helical transport barriers with maximum electron temperature around 1 keV develop in this region. The energy confinement time increases by a factor of 4 with respect to the lower-current, multi-helical conditions. The properties of the new helical state scale favourably with the current, thus opening promising perspectives for the higher current experiments planned for the near future
Current filaments in turbulent magnetized plasmas
No full textDirect measurements of current density perturbations associated with non-linear phenomena in magnetized plasmas can be carried out using in situ magnetic measurements. In this paper we report such measurements for three different kinds of phenomena. Current density fluctuations in the edge density gradient region of a fusion plasma confined in reversed field pinch configuration and in a density gradient region in the Earth magnetosphere are measured and compared, showing that in both environments they can be attributed to drift-Alfvén vortices. Current structures associated with reconnection events measured in a reversed field pinch plasma and in the magnetosheath are detected and compared. Evidence of current filaments occurring during ELMs in an H-mode tokamak plasma is displayed
Integration of the state observer RAPTOR in the real-time MARTe framework at RFX-mod
No full textThe RAPTOR - RApid Plasma Transport simulatOR code is a model-based control-oriented code that predicts Tokamak plasma profile evolution in real-time. One of its key applications is in a state observer, where the real-time predictions are combined with the measurements of the available diagnostics, yielding a complete estimate of the plasma profiles. The state observer RAPTOR is currently installed in the real-time control system of TCV, where it has been originally developed, ASDEX-Upgrade and recently RFX-mod. The latter has pioneered its integration in the real-time MARTe - Multi-threaded Application Real-Time executor framework, which will be the topic of this work. Thanks to this, RFX-mod can now contribute to develop integrated control techniques based on the state observer RAPTOR to avoid disruptions, which are highly reproducible in q(a) <2 RFX-mod Tokamak plasmas if they are left uncontrolled
Real-time simulation of internal profiles in the presence of sawteeth using the RAPTOR code and applications to ASDEX Upgrade and RFX-mod
No full textActive MHD control experiments in RFX-mod
No full textThe RFX reversed field pinch experiment has been modified (RFX-mod) to address specific issues of active control of MHD instabilities. A thin shell (τBv∼50 ms) has replaced the old thick one (τBv∼500 ms) and 192 (4 poloidal × 48 toroidal) independently powered saddle coils surround the thin shell forming a cage completely covering the torus. This paper reports the results obtained during the first year of operation. The system has been used with various control scenarios including experiments on local radial field cancellation over the entire torus surface to mimic an ideal wall (‘virtual shell’) and on single and multiple mode feedback control. Successful virtual shell operation has been achieved leading to: a 3-fold increase in pulse length and well controlled 300 ms pulses(∼6 shell times) up to ∼1 MA plasma current; one order of magnitude reduction of the dominant radial field perturbations at the plasma edge and correspondingly 100% increase in global energy confinement time. Robust feedback stabilization of resistive wall modes has been demonstrated in conditions where rotation does not play a role and multiple unstable modes are present
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