9 results on '"F.I. Parra"'
Search Results
2. Kinetic-ballooning-limited pedestals in spherical tokamak plasmas
- Author
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J.F. Parisi, W. Guttenfelder, A.O. Nelson, R. Gaur, A. Kleiner, M. Lampert, G. Avdeeva, J.W. Berkery, C. Clauser, M. Curie, A. Diallo, W. Dorland, S.M. Kaye, J. McClenaghan, and F.I. Parra
- Subjects
pedestal prediction ,gyrokinetics ,ideal MHD ,spherical tokamaks ,NSTX ,Nuclear and particle physics. Atomic energy. Radioactivity ,QC770-798 - Abstract
A theoretical model is presented that for the first time matches experimental measurements of the pedestal width-height Diallo scaling in the low-aspect-ratio high- β tokamak NSTX. Combining linear gyrokinetics with self-consistent pedestal equilibrium variation, kinetic-ballooning, rather than ideal-ballooning plasma instability, is shown to limit achievable confinement in spherical tokamak pedestals. Simulations are used to find the novel Gyrokinetic Critical Pedestal constraint, which determines the steepest pressure profile a pedestal can sustain subject to gyrokinetic instability. Gyrokinetic width-height scaling expressions for NSTX pedestals with varying density and temperature profiles are obtained. These scalings for STs depart significantly from that of conventional aspect ratio tokamaks.
- Published
- 2024
- Full Text
- View/download PDF
3. Density profiles in stellarators: an overview of particle transport, fuelling and profile shaping studies at TJ-II
- Author
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J.A. Alonso, D. Alegre, J. Alonso, R. Antón, A. Arias-Camisón, E. Ascasíbar, A. Baciero, J.M. Barcala, M. Barnes, E. Blanco, L. Bueno, A. Bustos, S. Cabrera, E. de la Cal, I. Calvo, A. Cappa, D. Carralero, R. Carrasco, B. Carreras, R. Castro, A. de Castro, L. Cebrián, M. Chamorro, A.A. Chmyga, P. Colino, J. Duque, F.J. Escoto, T. Estrada, A. Fernández, J. Fraguas, J.M. Fontdecaba, A. Gabriel, L. García, I. García-Cortés, R. García-Gómez, J.M. García-Regaña, G. Godino-Sedano, J. Gómez-Manchón, A. González, A. González-Jerez, V. Guisse, J. Hernández-Sánchez, J. Hernanz, C. Hidalgo, P. Ivanova, A. Jiménez-Denche, D. Jiménez-Rey, G. Kocsis, M. Koepke, A.S. Kozachek, F. Lapayese, M. Liniers, D. López, D. López-Bruna, B. López-Miranda, E. de la Luna, E. Maragkoudakis, F. Martín-Díaz, G. Martín-Gómez, J. Martínez-Fernández, K.J. McCarthy, F. Medina, D. Medina-Roque, M. Medrano, P. Méndez, F.J. Miguel, B. van Milligen, A. Molinero, G. Motojima, S. Mulas, M. Navarro, I. Nedzelskiy, R. Nuñez, M. Ochando, E. Oyarzábal, J.L. de Pablos, F. Palomares, N. Panadero, F.I. Parra, C. Pastor, I. Pastor, A. de la Peña, R. Peralta, A. Pereira, P. Pons-Villalonga, A.B. Portas, E. Poveda, F.J. Ramos, G.A. Rattá, M. Redondo, C. Reynoso, E. Rincón, J. de la Riva, C. Rodríguez-Fernández, A. Ros, E. Sánchez, J. Sánchez, E. Sánchez-Sarabia, J.A. Sebastián, E.R. Solano, A. Soleto, T. Szepesi, F.L. Tabarés, D. Tafalla, H. Takahashi, N. Tamura, H. Thienpondt, A. Tolkachev, V. Tribaldos, R. Unamuno, J. Varela, J. Vega, J.L. Velasco, and I. Voldiner
- Subjects
particle transport ,fuelling ,cryogenic pellet injection ,stellarator ,Nuclear and particle physics. Atomic energy. Radioactivity ,QC770-798 - Abstract
We provide an overview of activities carried out at the TJ-II stellarator for improving our understanding of- and developing plasma physics models for particle density profiles in stellarators. Namely, we report on recent progress in turbulent particle transport simulation, validation of pellet deposition models, density profile shaping for performance control and new experimental techniques for edge turbulence and plasma-neutral interaction.
- Published
- 2024
- Full Text
- View/download PDF
4. Robust stellarator optimization via flat mirror magnetic fields
- Author
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J.L. Velasco, I. Calvo, E. Sánchez, and F.I. Parra
- Subjects
robust ,stellarator ,optimization ,flat mirror ,reactor ,Nuclear and particle physics. Atomic energy. Radioactivity ,QC770-798 - Abstract
Stellarator magnetic configurations need to be optimized in order to meet all the required properties of a fusion reactor. In this work, it is shown that a flat-mirror quasi-isodynamic (QI) configuration (i.e. a QI configuration with sufficiently small radial variation of the mirror term) can achieve small radial transport of energy and good confinement of bulk and fast ions even if it is not very close to perfect omnigeneity, and for a wide range of plasma scenarios, including low β and small radial electric field. This opens the door to constructing better stellarator reactors. On the one hand, they would be easier to design, as they would be robust against error fields. On the other hand, they would be easier to operate since, both during startup and steady-state operation, they would require less auxiliary power, and the heat loads on plasma-facing components caused by fast ion losses would be reduced to acceptable levels.
- Published
- 2023
- Full Text
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5. Three-Dimensional Inhomogeneity of Electron-Temperature-Gradient Turbulence in the Edge of Tokamak Plasmas
- Author
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J.F. Parisi, F.I. Parra, C.M. Roach, M.R. Hardman, A.A. Schekochihin, I.G. Abel, N. Aiba, J. Ball, M. Barnes, B. Chapman-Oplopoiou, D. Dickinson, W. Dorland, C. Giroud, D.R. Hatch, J.C. Hillesheim, J. Ruiz Ruiz, S. Saarelma, D. St-Onge, and null JET Contributors
- Subjects
Nuclear and High Energy Physics ,fluctuations ,mode turbulence ,FOS: Physical sciences ,topography of turbulence ,Condensed Matter Physics ,microturbulence ,Physics - Plasma Physics ,finite aspect ratio ,Plasma Physics (physics.plasm-ph) ,magnetic geometry ,pedestal turbulence ,instabilities ,Physics::Plasma Physics ,plasma turbulence ,confinement ,transport ,Physics::Space Physics ,multiscale turbulence ,electron-temperature-gradient instability ,simulations ,tokamaks ,flow shear ,driven - Abstract
Nonlinear multiscale gyrokinetic simulations of a Joint European Torus edge pedestal are used to show that electron-temperature-gradient (ETG) turbulence has a rich three-dimensional structure, varying strongly according to the local magnetic-field configuration. In the plane normal to the magnetic field, the steep pedestal electron temperature gradient gives rise to anisotropic turbulence with a radial (normal) wavelength much shorter than in the binormal direction. In the parallel direction, the location and parallel extent of the turbulence are determined by the variation in the magnetic drifts and finite-Larmor-radius (FLR) effects. The magnetic drift and FLR topographies have a perpendicular-wavelength dependence, which permits turbulence intensity maxima near the flux-surface top and bottom at longer binormal scales, but constrains turbulence to the outboard midplane at shorter electron-gyroradius binormal scales. Our simulations show that long-wavelength ETG turbulence does not transport heat efficiently, and significantly decreases overall ETG transport -- in our case by $\sim$40 \% -- through multiscale interactions., 17 pages, 14 figures
- Published
- 2022
6. A novel approach to radially global gyrokinetic simulation using the flux-tube code $\texttt{stella}$
- Author
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D.A. St-Onge, M. Barnes, and F.I. Parra
- Subjects
Plasma Physics (physics.plasm-ph) ,Computational Mathematics ,Numerical Analysis ,Physics and Astronomy (miscellaneous) ,Applied Mathematics ,Modeling and Simulation ,FOS: Physical sciences ,Computational Physics (physics.comp-ph) ,Physics - Computational Physics ,Physics - Plasma Physics ,Computer Science Applications - Abstract
A novel approach to global gyrokinetic simulation is implemented in the flux-tube code $\texttt{stella}$. This is done by using a subsidiary expansion of the gyrokinetic equation in the perpendicular scale length of the turbulence, originally derived by Parra and Barnes [Plasma Phys. Controlled Fusion, $\textbf{57}$ 054003, 2015], which allows the use of Fourier basis functions while enabling the effect of radial profile variation to be included in a perturbative way. Radial variation of the magnetic geometry is included by utilizing a global extension of the Grad-Shafranov equation and the Miller equilibrium equations which is obtained through Taylor expansion. Radial boundary conditions that employ multiple flux-tube simulations are also developed, serving as a more physically motivated replacement to the conventional Dirichlet radial boundary conditions that are used in global simulation. It is shown that these new boundary conditions eliminate much of the numerical artefacts generated near the radial boundary when expressing a non-periodic function using a spectral basis. We then benchmark the new approach both linearly and nonlinearly using a number of standard test cases., 10 figures, 1 table
- Published
- 2022
7. Electrostatic gyrokinetic simulations in Wendelstein 7-X geometry: benchmark between the codes stella and GENE
- Author
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A. González-Jerez, P. Xanthopoulos, J.M. García-Regaña, I. Calvo, J. Alcusón, A. Bañón Navarro, M. Barnes, F.I. Parra, and J. Geiger
- Subjects
Plasma Physics (physics.plasm-ph) ,FOS: Physical sciences ,Condensed Matter Physics ,Physics - Plasma Physics - Abstract
The first experimental campaigns have proven that, due to the optimization of the magnetic configuration with respect to neoclassical transport, the contribution of turbulence is essential to understand and predict the total particle and energy transport in Wendelstein 7-X (W7-X). This has spurred much work on gyrokinetic modelling for the interpretation of the available experimental results and for the preparation of the next campaigns. At the same time, new stellarator gyrokinetic codes have just been or are being developed. It is therefore desirable to have a sufficiently complete, documented and verified set of gyrokinetic simulations in W7-X geometry against which new codes or upgrades of existing codes can be tested and benchmarked. This paper attempts to provide such a set of simulations in the form of a comprehensive benchmark between the recently developed code stella and the well-established code GENE. The benchmark consists of electrostatic gyrokinetic simulations in the W7-X magnetic geometry and includes different flux tubes, linear ion-temperature-gradient (ITG) and trapped-electron-mode stability analyses, computation of linear zonal-flow responses and calculation of ITG-driven heat fluxes.
- Published
- 2022
8. ASCOT5 simulations of neutral beam heating and current drive in the TJ-II stellarator
- Author
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S. Mulas, Á. Cappa, J. Kontula, D. López-Bruna, I. Calvo, F.I. Parra, M. Liniers, T. Kurki-Suonio, and M. Mantsinen
- Subjects
Nuclear and High Energy Physics ,Condensed Matter Physics - Abstract
The TJ-II stellarator neutral-beam injection (NBI) system, vacuum vessel and magnetic configuration have been included in the orbit-following Monte Carlo code ASCOT5 to simulate neutral-beam heating and current drive for high-density NBI plasmas. Co- and counter-injection beams are simulated separately. A scan in both electron density and temperature is carried out within the range of values corresponding to realistic high-density NBI plasmas, for which a low level of fast-ion losses due to charge-exchange reactions is expected, since the version of ASCOT5 used in the paper does not include such processes. The rest of the kinetic profiles (ion temperature, radial electric field and effective charge) are kept fixed. The initial distribution of markers shows that the amount of available power in the plasma carried by the beam ions depends slightly on the electron temperature and on the injection direction (co/counter). The steady-state fast-ion distribution function is obtained and used to calculate the three-dimensional fast-ion density, the neutral-beam driven current and the amount of power deposited to the plasma in the two injection scenarios. These three quantities are higher in the counter-injected case due to a lower amount of promptly lost particles. The neutral-beam current drive (NBCD) has been calculated using the fast-ion beam current given by ASCOT5 and the electron return current, which is computed with the analytic solution of the drift kinetic equation for electrons in the presence of fast ions in the low-collisionality regime. Neither the calculated fast-ion density nor the NBCD are flux functions, in consistency with the fact that fast-ion drift surfaces and flux surfaces are generally not aligned.
- Published
- 2022
- Full Text
- View/download PDF
9. Dependence of intrinsic rotation reversals on collisionality in MAST.
- Author
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J.C. Hillesheim, F.I. Parra, M. Barnes, N.A. Crocker, H. Meyer, W.A. Peebles, R. Scannell, A. Thornton, and Team, the MAST
- Subjects
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COLLISIONS (Nuclear physics) , *TOKAMAKS , *MOMENTUM (Mechanics) , *BACKSCATTERING , *PLASMA gases , *FLUCTUATIONS (Physics) - Abstract
Tokamak plasmas rotate even without external injection of momentum. A Doppler backscattering system installed at MAST has allowed this intrinsic rotation to be studied in ohmic L-mode and H-mode plasmas, including the first observation of intrinsic rotation reversals in a spherical tokamak. Experimental results are compared to a novel 1D model, which captures the collisionality dependence of the radial transport of toroidal angular momentum due to the effect of neoclassical flows on turbulent fluctuations. The model is able to accurately reproduce the change in sign of core toroidal rotation, using experimental density and temperature profiles from shots with rotation reversals as inputs and no free parameters fit to experimental data. [ABSTRACT FROM AUTHOR]
- Published
- 2015
- Full Text
- View/download PDF
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