A5020224830- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Particle accelerators and beam dynamics
- Solar and Space Plasma Dynamics
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Physics of Superconductivity and Magnetism
- Laser-induced spectroscopy and plasma
- Pulsed Power Technology Applications
- Nuclear Physics and Applications
- Nuclear Materials and Properties
- Gyrotron and Vacuum Electronics Research
- Meteorological Phenomena and Simulations
- Geomagnetism and Paleomagnetism Studies
- Engineering Applied Research
- Fluid Dynamics and Turbulent Flows
- Fish biology, ecology, and behavior
- Oceanographic and Atmospheric Processes
- Geophysics and Sensor Technology
- Radiative Heat Transfer Studies
- Atmospheric and Environmental Gas Dynamics
- Vacuum and Plasma Arcs
CEA Cadarache
2014-2023
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2014-2023
Institut de Recherche sur la Fusion par Confinement Magnétique
2010-2023
Max Planck Institute for Plasma Physics
2023
Centre National de la Recherche Scientifique
2021
Aix-Marseille Université
2021
Royal Military Academy
2020
Columbia University
2018
Centre de Physique Théorique
2008-2018
Centre de Physique Théorique
2008-2018
CRONOS is a suite of numerical codes for the predictive/interpretative simulation full tokamak discharge. It integrates, in modular structure, 1D transport solver with general 2D magnetic equilibria, several heat, particle and impurities models, as well momentum sources. This paper gives first comprehensive description suite: overall structure code, main available details on workflow implementation. Some examples applications to analysis experimental discharges predictions ITER scenarios are...
Abstract The ramp-up is a critical phase in the operations of Tokamak, during which engineering and physics aspects must be taken into account to ensure stability, minimize flux consumption avoid disruptions. Predicting phases faces challenges such as nonlinearity, uncertainty on boundary initial conditions changes magnetic equilibrium. Our work uses High-Fidelity Pulse Simulator (HFPS), Python workflow based JINTRAC. input output are machine code generic IMAS data format. HFPS predicts...
In the European fusion roadmap, ITER is followed by a demonstration power reactor (DEMO), for which conceptual design under development. This paper reports first results of coherent effort to develop relevant physics knowledge that (DEMO Physics Basis), carried out experts. The program currently includes investigations in areas scenario modeling, transport, MHD, heating & current drive, fast particles, plasma wall interaction and disruptions.
Abstract The non-linear reduced four-field RMHD model in cylindrical geometry was extended to include plasma rotation, neoclassical poloidal viscosity and two fluid diamagnetic effects. Interaction of the static resonant magnetic perturbations (RMPs) with rotating plasmas tokamaks studied. self-consistent evolution equilibrium electric field due RMP penetration is taken into account model. It demonstrated that pedestal region steep pressure gradients, mean flows perpendicular field, which...
Turbulence in hot magnetized plasmas is shown to generate permeable localized transport barriers that globally organize into the so-called "ExB staircase" [G. Dif-Pradalier et al., Phys. Rev. E, 82, 025401(R) (2010)]. Its domain of existence and dependence with key plasma parameters discussed theoretically. Based on these predictions, staircases are observed experimentally Tore Supra tokamak by means high-resolution fast-sweeping X-mode reflectometry. This observation strongly emphasizes...
With WEST (Tungsten Environment in Steady State Tokamak) (Bucalossi et al 2014 Fusion Eng. Des. 89 907–12), the Tore Supra facility and team expertise (Dumont Plasma Phys. Control. 56 075020) is used to pave way towards ITER divertor procurement operation. It consists implementing a configuration installing ITER-like actively cooled tungsten monoblocks tokamak, taking full benefit of its unique long-pulse capability. user platform, open all partners. This paper describes physics basis WEST:...
METIS is a numerical code aiming at fast full tokamak plasma analyses and predictions. It combines 0D scaling-law normalised heat particle transport with 1D current diffusion modelling 2D equilibria. contains several heat, impurities models, as well particle, momentum sources, which allow faster than real time scenario simulations. This paper gives first comprehensive description of the suite: overall structure code, main available details on simulation workflow implementation. Some examples...
This paper presents the results of three-dimensional fluid global simulations electrostatic ion turbulence in tokamaks with reversed magnetic shear. It is found that a transport barrier appears at location shear reversal. due to rarefaction resonant surfaces this region. For same reason, more pronounced when minimum safety factor simple rational number. The broadened by velocity effects. also large-scale events hardly cross barrier. Finally, significant amount toroidal rotation generated...
The formation of internal transport barriers (ITBs) has been experimentally associated with the presence rational q surfaces in both JET and ASDEX Upgrade. triggering mechanisms are related to occurrence magneto-hydrodynamic (MHD) instabilities such as mode coupling fishbone activity. These events could locally modify poloidal velocity increase transiently shearing rate values comparable linear growth ion temperature gradient modes. For reversed magnetic shear scenarios, ITB emergence occurs...
Extensive linear and non-linear gyrokinetic simulations magnetohydrodynamic (MHD) analyses performed for JET hybrid discharges with improved confinement have shown that the large population of fast ions found in plasma core under particular heating conditions has a strong impact on microturbulence edge MHD by reducing ion heat fluxes increasing pedestal pressure feedback mechanism. In case ITER like wall, it is how this mechanism plays decisive role transition to regimes can explain weak...
Abstract The influence of rotation, collisionality and trapped particle fraction on the magnitude direction neoclassical impurity transport in tokamaks is analyzed using an extensive database drift-kinetic simulations with NEO code. It shown that operational window opens at sufficiently high Mach number low collisionality, where temperature screening impurities increases higher rotation. If increases, this effect quickly lost gradient then drives inward flux when rotation present. boundary...
Disruptions are a major threat for future tokamaks, including ITER. Disruption-generated heat loads, electromagnetic forces and runaway electrons will not be tolerable next-generation devices. Massive noble gas injection is foreseen as standard mitigation system these tokamaks. Disruption experiments have been carried out on Tore Supra to study various scenarios investigate jet penetration mixing. Comparisons of different gases (He, Ne, Ar, He/Ar mixture) amounts (from 5 500 Pa m 3 ) were...
Self-consistent transport simulation of ITER scenarios is a very important tool for the exploration operational space and scenario optimisation. It also provides an assessment compatibility developed (which include fast transient events) with machine constraints, in particular poloidal field (PF) coil system, heating current drive (H&CD), fuelling particle energy exhaust systems. This paper discusses results predictive modelling all reference variants using two suite linked equilibrium...
Abstract The choice of first wall material is paramount importance for the plasma start-up conditions in ITER and future fusion power plants. In this context, present work focuses on correlations between impurity sources total radiated during tungsten (W) Environment Steady-state Tokamak (WEST). objective to highlight experimental indications a preferable combination scenario materials. Until 2019, WEST featured full high Z with all limiters exposing only W surfaces plasma. To study impact...
Abstract The full W environment that is now foreseen for ITER puts strong emphasis on experimental results obtained in present devices similar conditions. In this context, the WEST tokamak well equipped to bring key contributions preparation of operation, thanks its capability perform long pulses dominant electron heating, torque-free scheme based RF systems, and ITERgrade actively cooled divertor. Recent interest cover understanding tungsten contamination evaluation conditioning methods,...
Abstract A new record was set on the WEST Tokamak, designed to operate long duration plasmas in a tungsten (W) environment, with an injected energy of 1.15 GJ and plasma 364 s. Scenario development supported by integrated modeling using High Fidelity Plasma Simulator (HFPS), European IMAS-coupled version JETTO/JINTRAC, which integrates physics-driven modules into unified framework. In particular, reduced model for Lower-Hybrid heating Current-Drive (LHCD) quasi-linear turbulent transport...
Internal transport barriers (ITBs) can be produced in JET by the application of strong additional heating during current rise phase plasma discharge. Using up to 3 MW lower hybrid power tailor q-profile prior main phase, a large variety q-profiles ranging from low positive negative central shear have been obtained (0.4 MA s−1). With magnetic s = (r/q)(dr/dq), analysis ITB triggering reveals correlation between formation and q min reaching an integer value (q 2 or 3). This observation is...
Quasi-steady operation has been achieved at JET in the high-confinement regime with internal transport barriers (ITBs). The ITB maintained up to 11 s. This duration, much larger than energy confinement time, is already approaching a current resistive time. high-performance phase limited only by plant constraints. radial profiles of thermal electron and ion pressures have steep gradients typically mid-plasma radius. A large fraction non-inductive (above 80%) sustained throughout poloidal beta...
Quasistationary operation has been achieved on the Joint European Torus tokamak in internal-transport-barrier (ITB) scenarios, with discharge time limited only by plant constraints. Full current drive was obtained over all high performance phase using lower hybrid drive. For first feedback control total pressure and electron temperature profile implemented using, respectively, neutral beams ion-cyclotron waves. Although impurity accumulation could be a problem steady state ITBs, these...
Extensive physics analysis and modelling has been undertaken for the typical operational regimes of tokamak devices JET JT-60U with aim extrapolating present day experiments to JT-60SA, which shares important characteristics both tokamaks. A series representative discharges two scenarios, H-mode hybrid, have used this purpose. Predictive simulations core turbulence, particle transport, current diffusion pedestal pressure carried out different combinations models. The ability models...
Abstract The consequences of tungsten (W) melting on divertor lifetime and plasma operation are high priority issues for ITER. Sustained controlled W-melting experiment has been achieved the first time in WEST a poloidal sharp leading edge an actively cooled ITER-like facing unit (PFU). A series dedicated power steady state discharges were performed to reach point tungsten. was exposed parallel heat flux about 100 MW.m −2 up 5 s providing melt phase 2 without noticeable impact (radiated...
Abstract In the full tungsten environment of WEST, during its first phase operation, around 25% pulses exhibited a rapid central electron temperature collapse. phase, WEST plasmas were mostly heated by lower hybrid current drive (LHCD) and ion cyclotron resonance heating (ICRH). this publication, collapsing are analysed to understand key actuators at play. Experimentally, an initial slow reduction due density increase is observed, while profile flat constant in time. Then, radiative collapse...