J. Ayllon-Guerola
A5084255396- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Fusion materials and technologies
- Nuclear reactor physics and engineering
- Radiation Detection and Scintillator Technologies
- Nuclear Physics and Applications
- Laser-Plasma Interactions and Diagnostics
- Particle Detector Development and Performance
- Atomic and Subatomic Physics Research
- Plasma Diagnostics and Applications
- Advanced Data Storage Technologies
- Integrated Energy Systems Optimization
- Solar and Space Plasma Dynamics
- Radiation Effects in Electronics
- Spacecraft and Cryogenic Technologies
- Frequency Control in Power Systems
- Geomagnetism and Paleomagnetism Studies
- Viral Infections and Vectors
- Heat transfer and supercritical fluids
- Electromagnetic Launch and Propulsion Technology
Universidad de Sevilla
2016-2025
Centro Nacional de Aceleradores
2017-2024
Junta de Andalucía
2017-2022
Consejo Superior de Investigaciones Científicas
2017-2019
Abstract The research program of the TCV tokamak ranges from conventional to advanced-tokamak scenarios and alternative divertor configurations, exploratory plasmas driven by theoretical insight, exploiting device’s unique shaping capabilities. Disruption avoidance real-time locked mode prevention or unlocking with electron-cyclotron resonance heating (ECRH) was thoroughly documented, using magnetic radiation triggers. Runaway generation high- Z noble-gas injection runaway dissipation...
A simple model for the instrument function of scintillator-based fast-ion loss detectors (FILD) has been developed which accounts orbit trajectories in 3D detector geometry and scintillator response. It allows us to produce synthetic FILD signals a direct comparison between experiments simulations. The uses weight formalism relate velocity-space distribution losses reaching pinhole pattern obtained experimentally, can be understood as distortion due finite resolution system. tool recover...
Within the EUROfusion MST1 work package, a series of experiments has been conducted on AUG and TCV devices to disentangle role plasma fueling shape for onset small ELM regimes. On both devices, regimes with high confinement are achieved if only two conditions fulfilled at same time. Firstly, density separatrix must be large enough (), leading pressure profile flattening separatrix, which stabilizes type-I ELMs. Secondly, magnetic configuration close double null (DN), reduction shear in...
Abstract Hybrid fusion power plants able to produce hydrogen and electricity are proposed here as a way of decarbonising the fossil-fuel-dominated primary energy market improve plant economics. The main cost drivers based on spherical tokamak have been identified using statistical analysis (Morris Sobol methods) from wide range cases obtained with systems code PROCESS. Showing relevance parameters such 
β, A, B T max .

Three scenarios advancing technophysical...
A new spherical tokamak, the SMall Aspect Ratio Tokamak (SMART), is currently being designed at University of Seville. The goal machine to achieve a toroidal field 1 T, plasma current 500 kA and pulse length ms for with major radius 0.4 m minor 0.25 m. This contribution presents design coils power supplies machine. foresees central solenoid, 12 8 poloidal coils. Taking waveforms these set as starting point, each them has been withstand Joule heating during tokamak operation time. An...
A conceptual design of a reciprocating fast-ion loss detector for ITER has been developed and is presented here. Fast-ion orbit simulations in 3D magnetic equilibrium up-to-date first wall have carried out to revise the measurement requirements lost alpha monitor ITER. In agreement with recent observations, here suggest that pitch-angle resolution ∼5° might be necessary identify mechanisms. Synthetic measurements including realistic alpha-particle as well neutron gamma fluxes predict...
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...
A new scintillator based fast-ion loss detector (FILD) system has been designed for the Wendelstein 7-X (W7-X) stellarator. The mechanical design of is presented here along with engineering analyses system. This includes an assessment structural loads which also considers electromagnetic forces calculated possible disruption scenarios as well a mode frequency analysis Furthermore, thermal characteristics actively cooled probe head under prescribed steady state and transient heat presented....
The SMall Aspect Ratio Tokamak (SMART) device is a new compact (plasma major radius Rgeo≥0.40 m, minor a≥0.20 aspect ratio A≥1.7) spherical tokamak, currently in development at the University of Seville. SMART has been designed to achieve magnetic field plasma center up Bϕ=1.0 T with currents Ip=500 kA and pulse length τft=500 ms. A wide range shaping configurations are envisaged, including triangularities between −0.50≤δ≤0.50 elongations κ≤2.25. Control achieved through four axially...
Abstract A large superconducting machine, JT-60SA has been constructed to provide major contributions the ITER program and DEMO design. For success of project fusion reactor, understanding development plasma controllability in relevant higher beta regimes are essential. focused on for scenario risk mitigation as well investigating regimes. This paper summarizes high research priorities strategy project. Recent works simulation studies prepare physics control experiments presented, such...
The design and unique feature of the first fast-ion loss detector (FILD) for Mega Amp Spherical Tokamak - Upgrade (MAST-U) is presented here. MAST-U FILD head mounted on an axially angularly actuated mechanism that makes it possible to independently adapt orientation [0°, 90°] radial position [1.40 m, 1.60 m] head, i.e., its collimator, thus maximizing velocity-space coverage in a broad range plasma scenarios with different q95. 3D geometry has been optimized detect losses from neutral beam...
A new diagnostic technique that allows to obtain absolute fluxes of fast-ion losses measured with absolutely calibrated scintillator based loss detectors (FILD) is presented here. First have been obtained in the ASDEX Upgrade tokamak. An instrument function includes efficiency, collimator geometry, optical transmission and camera efficiency has constructed. The response deuterium ions relevant energy range fast-ions characterized using a tandem accelerator. Absolute flux neutral beam...
A new reciprocating scintillator based fast-ion loss detector has been installed a few centimeters above the outer divertor of ASDEX Upgrade tokamak and between two its lower Edge Localized Modes (ELM) mitigation coils. The head containing screen, Faraday cup, calibration lamp, collimator systems are on motorized system that can adjust position via remote control in plasma discharges. Orbit simulations used to optimize geometry velocity-space coverage. image is transferred light acquisition...
An Imaging Neutral Particle Analyzer (INPA) diagnostic has been designed for the ASDEX Upgrade (AUG) tokamak. The AUG INPA will measure fast neutrals escaping plasma after charge exchange reactions. be ionized by a 20 nm carbon foil and deflected toward scintillator local magnetic field. use of neutral beam injector (NBI) as an active source provide radially resolved measurements, while component allow us to cover whole along NBI line with unprecedented phase-space resolution (<12 keV 8 cm)...
The SMall Aspect Ratio Tokamak (SMART) is a new spherical machine that currently under construction at the University of Seville aimed exploring negative vs positive triangularity prospects in Spherical Tokamaks (ST). operation SMART will cover three phases, with toroidal fields Bϕ≤ 1 T, inductive plasma currents up to Ip= 500 kA and pulse length ms, for R = 0.4 m, 0.25 m wide range shaping configurations (aspect ratio, 1.4 < R/a 3, elongation, κ≤ average triangularity, -0.6 ≤δ≤ 0.6). magnet...
A quantitative theoretical framework has been created to model neutral beam injection and fast ion losses in the Wendelstein 7-X (W7-X) stellarator, including a novel method develop synthetic diagnostics for loss detectors (FILDs) of many types, such as scintillating Faraday Cup FILDs. This is first time that this done stellarator geometry with level fidelity, providing way be predicted more precisely future experiments W7-X. Simulations signal seen by FILD have completed multiple W7-X...
Abstract Tokamak à configuration variable (TCV), recently celebrating 30 years of near-continual operation, continues in its missions to advance outstanding key physics and operational scenario issues for ITER the design future power plants such as DEMO. The main machine heating systems changes are first described. Then follow five sections: plasma scenarios. Base-Line (IBL) discharges, triangularity studies together with X3 N2 seeding. Edge localised mode suppression, a high radiation...
A conceptual design of a new diagnostic for the simultaneous space and time resolved measurement plasma density, potential poloidal magnetic field fluctuations at ASDEX Upgrade is proposed. The combines detection techniques standard heavy ion beam probes (HIBP) scintillator based fast loss detectors (FILD), making use an atomic to probe parameters with high spatio-temporal resolution. This approach takes advantage using neutral plate as system. combination these two makes more compact than...
A new scintillator-based fast-ion loss detector (FILD) has been deployed ∼45o below the midplane of ASDEX Upgrade tokamak. Port unavailability at this remote location requires an in-situ magnetically driven manipulator to move diagnostic head horizontally through scrape-off layer (SOL). The linear displacement is produced by externally energized coil, whose magnetic dipole tries align with toroidal component tokamak field. insertion given force balance between a retaining spring and...
A magnetically driven fast-ion loss detector system for the ASDEX Upgrade tokamak has been designed and will be presented here. The device is feedback controlled to adapt head position heat load physics requirements. Dynamic simulations have performed taking into account effects such as friction, coil self-induction, eddy currents. real time positioning control algorithm maximize operational window developed. This considers dynamical behavior mechanical resistance well measured predicted...
A conceptual design of a scintillator-based fast-ion loss detector (FILD) has been developed for the Wendelstein 7-X stellarator (W7-X). Simulations using Monte Carlo codes ASCOT5 and BEAMS3D have performed to calculate expected flux neutral beam injection (NBI)-generated fast hydrogen ions onto probe head. These fluxes calculated several magnetic field configurations as well insertion positions. At maximum position, both co- counter-going losses with high incident pitch angles are observed;...
An imaging neutral particle analyzer (INPA) has been installed in the ASDEX Upgrade (AUG) tokamak to provide simultaneous measurements of radial profile and energy confined fast-ion (FI) population. The INPA diagnostic leverages advantages analyzers (NPAs) FI loss detectors (FILDs) by measuring charge exchange (CX) neutrals ionized an ultrathin carbon foil is deflected into a scintillator local magnetic field. design this developed under series constraints, such as lack space hazardous...
A forward model to resolve the fast-ion loss velocity-space on a detector (FILD) probe head (FILDSIM) has been extended, making it possible perform real-time analysis of FILD data ("real-time FILDSIM"). Parametric pre-processing with FILDSIM enables mapping raw measurements distribution reaching probe, which depends local magnetic field at head. Such parametric facilitates study losses in stages discharge other than flat-top, such as ramp-up phase when changes cannot be neglected. Real-time...