A5100417519- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Superconducting Materials and Applications
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
- Solar and Space Plasma Dynamics
- Fluid Dynamics and Turbulent Flows
- Aerodynamics and Acoustics in Jet Flows
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Advanced materials and composites
- Nuclear Materials and Properties
- Diamond and Carbon-based Materials Research
- Metal and Thin Film Mechanics
- Atomic and Subatomic Physics Research
- Spacecraft and Cryogenic Technologies
- Ultrasonics and Acoustic Wave Propagation
- Computational Fluid Dynamics and Aerodynamics
- Structural Health Monitoring Techniques
- Radiation Detection and Scintillator Technologies
- Metallurgical Processes and Thermodynamics
- Ion-surface interactions and analysis
- Heat Transfer Mechanisms
University of Lisbon
2016-2025
Universidade Federal de Itajubá
2024
International Iberian Nanotechnology Laboratory
2023-2024
National Institute of Telecommunications
2024
Culham Centre for Fusion Energy
1997-2024
Universidade de Brasília
2024
Instituto Federal de Educação Ciência e Tecnologia da Paraíba
2024
Universidade do Estado do Rio Grande do Norte
2024
Universidade Federal do Rio Grande do Norte
2024
Culham Science Centre
2009-2024
The dependence of plasma transport and confinement on the main hydrogenic ion isotope mass is fundamental importance for understanding turbulent and, therefore, accurate extrapolations from present tokamak experiments, which typically use a single hydrogen isotope, to burning plasmas such as ITER, will operate in deuterium–tritium mixtures. Knowledge properties edge barrier formation species critical view initial, low-activation phase ITER operations or helium its implications subsequent...
The impact of carbon and beryllium/tungsten as plasma-facing components on plasma radiation, divertor power particle fluxes, neutral conditions in the divertors has been assessed JET both experimentally by edge fluid code simulations for plasmas low-confinement mode. In high-recycling studies show a 30% reduction total radiation scrape-off (SOL) layer when replacing (JET-C) with beryllium main chamber tungsten (JET-ILW). Correspondingly, at low-field side (LFS) plate two-fold increase...
For several reasons the challenge to keep loads first wall within engineering limits is substantially higher in DEMO compared ITER. Therefore pre-conceptual design development for that currently ongoing Europe needs be based on load estimates are derived employing most recent plasma edge physics knowledge.
Experiments in the tokamaks TEXTOR, CASTOR, T-10 and ISTTOK, as well reversed field pinch RFX have provided new complementary evidence on physics of universal mechanism E×B velocity shear stabilization turbulence, concomitant transport barrier formation radial conductivity by using various edge biasing techniques.
The first experimental evidence showing the connection between blob/hole formation and zonal-flow generation was obtained in edge plasma of JET tokamak. Holes as well blobs are observed to be born shear layer, where zonal-flows off meso-scale coherent structures, leading disconnection positive negative pressure perturbations. newly formed transport azimuthal momentum up gradient flow drive while moving outwards. During this process energy is transferred from structures zonal flows via...
This paper presents the experimental characterization of pedestal parameters, edge localized mode (ELM) energy, and particle losses from main plasma corresponding ELM energy fluxes on facing components for a series dedicated experiments in Joint European Torus (JET). From these experiments, it is demonstrated that simple hypothesis relating peeling-ballooning linear instability to not valid. Contrary previous observations at lower triangularities, small low collisionality have been obtained...
Long-distance coupling between edge parameters' fluctuations has been investigated in the TJ-II stellarator. Results show long-range correlations potential fluctuations, which are amplified by development of radial electric fields during transitions to improved-confinement regimes, whereas there is no correlation ion saturation current signals. These experimental findings suggest importance as a new fingerprint plasma behavior shear flows and key role amplify them.
This contribution summarises a number of aspects the experimental and modelling programme at JET aimed improving characterisation understanding ELM transport in scrape-off layer (SOL).Divertor target energy deposition asymmetries favouring inner for ion Bx∇B drift directed towards X-point are observed with infra-red (IR) thermography.Particle-in-Cell kinetic calculations parallel heat have been made range energies, showing detailed time response sheath transmission factors indicating that...
This paper presents the latest results on confinement studies in TJ-II stellarator. The inherently strong plasma–wall interaction of has been successfully reduced after lithium coating by vacuum evaporation. Besides H retention and low Z , Li was chosen because there exists a reactor-oriented interest this element, thus giving special relevance to investigation its properties. Li-coating led important changes plasma performance. Particularly, effective density limit NBI plasmas extended...
Recent experiments at JET combining reciprocating probe measurements upstream and infrared thermography the plasma-facing components (PFC) on plasmas in limiter configurations show that common approach to predicting power load underestimates heat flux contact point by a factor 1.5–3. The current model scaling laws used for onto first wall during ramp-up/down ITER are uncertain better understanding of transport PFCs is required. loads usually predicted projecting parallel associated with...
A stationary H-mode without edge localized modes (ELMs) has been recently achieved in the ASDEX Upgrade tokamak by applying central electron cyclotron resonance heating above L-H power threshold with adequate fueling. It is naturally obtained favorable ∇B configuration and several features which are desirable for future reactors, such as dominant heating, low input torque, possibility of access at power, good energy confinement (), high density no impurity accumulation despite absence ELMs....
Abstract We present an overview of results from a series L–H transition experiments undertaken at JET since the installation ITER-like-wall (JET-ILW), with beryllium wall tiles and tungsten divertor. Tritium, helium deuterium plasmas have been investigated. Initial in tritium show ohmic transitions low density power threshold for ( P LH ) is lower than ones densities, while we still lack contrasted data to provide scaling high densities. In there notable shift which minimum <?CDATA...
Abstract The recent deuterium–tritium campaign in JET-ILW (DTE2) has provided a unique opportunity to study the isotope dependence of L-H power threshold an ITER-like wall environment (Be and W divertor). Here we present results from dedicated transition experiments at JET-ILW, documenting tritium plasmas, comparing them with matching deuterium hydrogen datasets. From earlier it is known that as plasma isotopic composition changes deuterium, through varying deuterium/hydrogen concentrations,...
Abstract In order to extend the enhanced D-Alpha H-mode future devices, it is crucial understand properties of main signature this regime, quasicoherent mode (QCM), that likely clamps pressure gradient below ideal magnetohydrodynamic limit. The turbulent character QCM investigated with scanning probes in ASDEX Upgrade. Analysis reveals multi-faced spans both confined region (where radial electric field negative) and near scrape-off layer (SOL) positive). Fluctuations density potential at...
Abstract Electron cyclotron resonance heating (ECRH) staircase discharges in strongly shaped plasmas were performed at the full-tungsten ASDEX Upgrade tokamak to investigate enhanced Dα (EDA) H-mode, a high-confinement regime without edge localized modes (ELMs) that exhibits numerous desirable qualities for future reactors. Heating power, fueling, and plasma current scans reveal rich dynamics as traverses different confinement regimes. The L-H transition typically occurs with brief I-phase,...
Abstract This study investigates the dependence of radial electric field (Er) on line-averaged density in JET L-mode plasmas, utilizing Doppler backscattering measurements. Density ramp discharges up to limit are analyzed investigate physical processes that determine edge Er profile. At low densities, profile at midplane exhibits a pronounced peak near scrape-off layer (SOL) and shallow well inside separatrix. As increases, SOL diminishes quickly deepens until Greenwald fraction fGW ≈ 0.8,...
O presente trabalho tem como objetivo reunir informações sobre o beneficiamento da tilápia do Nilo (Oreochromis niloticus), com ênfase nos requisitos de aproveitamento resíduos durante e após processo produção. A tilápia, sendo um alimento altamente perecível, demanda uma abordagem que garanta a manutenção sua qualidade desde captura até consumo. Investigando práticas tecnologias podem ser aplicadas para dos subprodutos rendimento, investigando aproveitamento. Enfatizando relevância...
Resumo: Este artigo tem como objetivo analisar a importância do sistema de ressocialização prisional no Estado Piauí, destacando suas principais iniciativas e desafios. Sabe-se que é um processo fundamental para reduzir reincidência criminal promover reintegração dos detentos à sociedade. Buscando, então, estudar avaliar as ações políticas aplicadas nesse ressocialização, pesquisa baseou-se em uma revisão bibliográfica, considerando legislações, estudos acadêmicos programas governamentais...
The radial profile of Reynolds stress has been measured in the plasma boundary region ISTTOK tokamak using a multiarray Langmuir probes. electrostatic component, proportional to cross correlation and poloidal fluctuating electric fields, shows gradient close velocity shear layer location. It is shown that this mechanism may drive significant flows region.
A theory-based scaling for the characteristic length of a circular, limited tokamak scrape-off layer (SOL) is obtained by considering balance between parallel losses and non-linearly saturated resistive ballooning mode turbulence driving anomalous perpendicular transport.The SOL size increases with plasma size, resistivity, safety factor q. The verified against flux-driven non-linear simulations, which reveal good agreement within wide range dimensionless parameters, including parameters...