A5084683187- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Solar and Space Plasma Dynamics
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Geomagnetism and Paleomagnetism Studies
- Fluid Dynamics and Turbulent Flows
- Neural dynamics and brain function
- Functional Brain Connectivity Studies
- EEG and Brain-Computer Interfaces
- Advanced machining processes and optimization
- Nuclear Materials and Properties
- Laser-induced spectroscopy and plasma
- Metal and Thin Film Mechanics
- Historical and Literary Studies
- Scientific Computing and Data Management
- Adhesion, Friction, and Surface Interactions
- Cell Image Analysis Techniques
- Advanced Machining and Optimization Techniques
- Advanced Surface Polishing Techniques
- Lattice Boltzmann Simulation Studies
Universidad de Guadalajara
2019-2025
Culham Science Centre
2015-2024
United Kingdom Atomic Energy Authority
2024
Institut de Recherche sur la Fusion par Confinement Magnétique
2019-2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2015-2024
CEA Cadarache
2015-2024
Max Planck Institute for Plasma Physics
2015-2023
National Centre for Nuclear Research
2021
École Polytechnique Fédérale de Lausanne
2016-2017
Japan External Trade Organization
2016
JOREK is a massively parallel fully implicit non-linear extended MHD code for realistic tokamak X-point plasmas. It has become widely used versatile studying large-scale plasma instabilities and their control developed in an international community. This article gives comprehensive overview of the physics models implemented, numerical methods applied solving equations studies performed with code. A dedicated section highlights some verification work done hierarchy different available...
A possible mechanism of edge localized modes (ELMs) mitigation by resonant magnetic perturbations (RMPs) is proposed based on the results nonlinear resistive magnetohydrodynamic modeling using jorek code, realistic JET-like plasma parameters and an RMP spectrum JET error-field correction coils (EFCC) with a main toroidal number n=2 were used in simulations. Without RMPs, large ELM relaxation obtained mainly due to most unstable medium-n ballooning mode. The externally imposed drives...
Abstract The plasma response to resonant magnetic perturbations (RMPs) in ASDEX Upgrade is modeled with the non-linear resistive MHD code JOREK, using input profiles that match those of experiments as closely possible. RMP configuration for which edge localized modes are best mitigated related largest kink observed near X-point modeling. On surfaces q = m / n , coupling between component ( > nq ) and found induce amplification perturbation. ergodicity 3D-displacement induced by can only...
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...
Nonstatic Neuron identity emerges from the complementary synaptic transcriptional architecture shaped by neuron signaling and surrounding non-neuronal cells. When signals a series of neurons are combined, they form circuits through which information flows, brain functioning occurs as superposition these neural circuits. To ensure proper communication function, develop phenotypes axonal projections electrophysiological behaviors, creating gradients that define regions allocate neurochemical...
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...
JOREK 3D non-linear MHD simulations of a D2 Massive Gas Injection (MGI) triggered disruption in JET are presented and compared detail to experimental data. The MGI creates an overdensity that rapidly expands the direction parallel magnetic field. It also causes growth islands (m/n=2/1 3/2 mainly) seeds 1/1 internal kink mode. O-points all island chains (including 1/1) located front MGI, consistently with observations. A burst activity peak plasma current take place at same time as...
Predictability of burning plasmas is a key issue for designing and building credible future fusion devices. In this context, an important effort physics understanding guidance being carried out in parallel to JET experimental campaigns H D by performing analyses modelling towards improvement the DT optimization JET-DT neutron yield born alpha particle physics. Extrapolations from recent experiments using maximum power available have been performed including some most sophisticated codes...
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...
The full dynamics of a multi-edge-localized-mode (ELM) cycle is modeled for the first time in realistic tokamak $X$-point geometry with nonlinear reduced MHD code jorek. diamagnetic rotation found to be instrumental stabilize plasma after an ELM crash and model cyclic reconstruction collapse pressure profile. relaxations are cyclically initiated each pedestal gradient crosses triggering threshold. Diamagnetic drifts also yield near-symmetric power deposition on inner outer divertor target...
In order to improve cross-field transport description, drifts and currents have been implemented in SOLEDGE2D–EIRENE. The derivation of an equation for the electric potential is recalled. resolution current tested a simple slab case. WEST divertor simulations forward-B reverse-B fields are also discussed. A significant increase ExB shear observed configuration that could explain favorable L-H transition this
Abstract Sheared flows are known to reduce turbulent transport by decreasing the correlation length and/or intensity of structures. The barrier that takes place at edge during improved regimes such as H mode, corresponds establishment a large shear radial electric field. In this context, shape field or more exactly perpendicular E × B velocity appears key element in accessing confinement regimes. paper, we present profile measured using Doppler back-scattering system plasma, dominated...
Abstract Achieving a successful plasma current ramp-up in full tungsten tokamak can be challenging due to the large core radiation (and resulting low temperature) that faced with this heavy metallic impurity if its relative concentration is too high. Nitrogen injection during of WEST discharges greatly improves temperature and magnetohydrodynamic (MHD) stability. Experimental measurements integrated simulations RAPTOR code, complemented QuaLiKiz neural network for computing turbulent...
The dynamics of a multi-edge localized mode (ELM) cycle as well the ELM mitigation by resonant magnetic perturbations (RMPs) are modeled in realistic tokamak X-point geometry with non-linear reduced MHD code JOREK. diamagnetic rotation is found to be key parameter enabling us reproduce cyclical plasma relaxations and model near-symmetric power deposition on inner outer divertor target plates consistently experimental measurements. Moreover, coupling RMPs unstable modes modify edge topology...
Edge Localized Modes (ELMs) rotating precursors were reported few milliseconds before an ELM crash in several tokamak experiments. Also, the reversal of filaments rotation at is commonly observed. In this article, we present a mathematical model that reproduces as well crash. Linear ballooning theory used to establish formula estimating velocity precursors. The linear study together with nonlinear magnetohydrodynamic simulations give explanation rotations observed experimentally. Unstable...
The pre-fusion power operation (PFPO) phase of ITER, as described in the ITER research plan with Staged Approach2, includes both hydrogen (H) and helium (He) plasma operations. In preparation for PFPO, WEST JET ran He campaigns to study plasma-wall interactions a tungsten environment. included back-and-forth transition between H or deuterium (D) allowing assessment achievable content well accessible wall reservoirs respective species. changeovers tokamak pulses fixed divertor configuration....
Heat flux profiles inferred from a reciprocating probe at the outer midplane of TCV tokamak during inner wall limited discharges feature radial fall-off lengths that shorten near last closed surface (LCFS) consistent with so-called narrow feature. The is significantly wider on outboard side compared measured by infrared thermography, so it difficult to discern main scrape-off layer After small shifts were applied for alignment, fraction power contained in matches between inboard and...
JT-60SA, the largest tokamak that will operate before ITER, has been designed and built jointly by Japan Europe, is due to start operation in 2020.Its main missions are support ITER exploitation contribute demonstration fusion reactor machine scenario design.Peculiar properties of JT-60SA its capability produce long-pulse, high-β, highly shaped plasmas.The preparation Research Plan, plasma scenarios, producing physics results not only relevant future experiments, but often constitute...
Abstract High power experiments, up to 9.2 MW with LHCD and ICRH, have been carried out in the full tungsten tokamak WEST. Quasi non inductive discharges achieved allowing extend plasma duration 53 s stationary conditions particular respect contamination. Transitions H mode are observed, H-modes lasting 4 obtained. The increase stored energy is weak since crossing separatrix close L–H threshold. Hot L plasmas (central temperature exceeding 3 keV) a confinement time following ITER L96 scaling...