I.S. Carvalho
A5016643376- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- High-Energy Particle Collisions Research
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Underwater Vehicles and Communication Systems
- Advanced Data Storage Technologies
- Nuclear Engineering Thermal-Hydraulics
- Solar and Space Plasma Dynamics
- BRCA gene mutations in cancer
- Anomaly Detection Techniques and Applications
- Genomics and Rare Diseases
- Atomic and Subatomic Physics Research
- Plasma and Flow Control in Aerodynamics
- Marine Biology and Ecology Research
- Cardiovascular Issues in Pregnancy
- Magnetic Field Sensors Techniques
- Error Correcting Code Techniques
- Electrostatic Discharge in Electronics
General Atomics (United States)
2022-2025
Max Planck Institute for Plasma Physics
2014-2024
ITER
2022-2024
University of Lisbon
2014-2024
United Kingdom Atomic Energy Authority
2021-2023
Culham Science Centre
2017-2023
Culham Centre for Fusion Energy
2017-2023
Instituto Superior Técnico
2006-2023
Instituto Politécnico de Lisboa
2023
Royal Military Academy
2020
Abstract The tokamak approach, utilizing a toroidal magnetic field configuration to confine hot plasma, is one of the most promising designs for developing reactors that can exploit nuclear fusion generate electrical energy 1,2 . To reach goal an economical reactor, reactor 3–10 simultaneously require reaching plasma line-averaged density above empirical limit—the so-called Greenwald 11 —and attaining confinement quality better than standard high-confinement mode 12,13 However, such...
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...
Abstract The JET hybrid scenario has been developed from low plasma current carbon wall discharges to the record-breaking Deuterium-Tritium plasmas obtained in 2021 with ITER-like Be/W wall. development started pure Deuterium refinement of current, and toroidal magnetic field choices succeeded solving heat load challenges arising 37 MW injected power ITER like environment, keeping radiation edge core controlled, avoiding MHD instabilities reaching high neutron rates. have re-run Tritium...
Burning plasmas with 500 MW of fusion power on ITER will rely partially detached divertor operation to keep target heat loads at manageable levels. Such regimes be maintained by a real-time control system using the seeding radiative impurities like nitrogen (N), neon or argon as actuator and one more diagnostic signals sensors. Recently, detachment has been successfully achieved in Type I ELMy H-mode JET-ITER-like wall discharges saturation current (Isat) measurements from Langmuir probes...
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...
The fusion-born alpha particle heating in magnetically confined fusion machines is a high priority subject for studies. self-heating of thermonuclear plasma by particles was observed recent deuterium-tritium (D-T) experiments on the joint European torus. This observation possible conducting so-called "afterglow" where transient yield achieved with neutral beam injection as only external source, and then termination at peak performance. allowed first direct evidence electron plasmas alphas to...
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 The reference ion cyclotron resonance frequency (ICRF) heating schemes for ITER deuterium–tritium (D-T) plasmas at the full magnetic field of 5.3 T are second harmonic and 3 He minority heating. wave-particle location these coincide central a wave 53 MHz T. Experiments have been carried out in major D-T campaign (DTE2) JET, its prior D campaigns, to integrate ICRF scenarios JET high-performance compare their performance with commonly used hydrogen (H) In 50:50 D:T plasmas, up 35% 5%...
Abstract The dimensionless isotope mass scaling experiment between pure Deuterium and Tritium plasmas with matched <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msup> <mml:mi>ρ</mml:mi> <mml:mo>∗</mml:mo> </mml:msup> </mml:math> , <mml:mi>ν</mml:mi> β n q <mml:msub> <mml:mi>T</mml:mi> <mml:mi>e</mml:mi> </mml:msub> <mml:mrow> <mml:mo>/</mml:mo> </mml:mrow> <mml:mi>i</mml:mi> has been achieved in JET L-mode dominant electron heating (NBI+ohmic) conditions....
Abstract This paper reports the first experiment carried out in deuterium–tritium addressing integration of a radiative divertor for heat-load control with good confinement. Neon seeding was time D–T plasma as part second campaign JET its Be/W wall environment. The technical difficulties linked to re-ionisation heat load are reported T and D–T. compares impact neon on plasmas their D counterpart detachment, localisation radiation, scrape-off profiles, pedestal structure, edge localised modes global
A constipação funcional é uma condição comum nas crianças e na maioria dos casos, resolvida com medicamentos laxativos, mudança dietética alta ingesta de fibras hidrica. Mas, existe subpopulação que pode apresentar refratariedade a estes tratamentos. estimulação elétrica nervosa transcutânea (TENS), atualmente modalidade tratamento não farmacológico promissora, sendo alvo muitos estudos Pediatria. O objetivo do estudo foi analisar literatura científica acerca da eficácia uso TENS para tratar...
Recent high-poloidal-beta (high-βP) experiments on DIII-D and EAST have made coordinated breakthroughs for high confinement quality at density near the Greenwald limit. Density gradient amplification of turbulence suppression βP can explain both these achievements. Experiments achieved fraction (fGr = line-averaged density/Greenwald density) above 1 simultaneously with normalized energy (H98y2) around 1.5, as required in fusion reactor designs but never before verified tokamak divertor...
Abstract JET returned to deuterium-tritium operations in 2023 (DTE3 campaign), approximately two years after DTE2. DTE3 was designed as an extension of JET's 2022-2023 deuterium campaigns, which focused on developing scenarios for ITER and DEMO, integrating in-depth physics understanding control schemes. These were evaluated with mixed D-T fuel, using the only remaining tritium-capable tokamak until its closure 2023. A core-edge-SOL integrated H-mode scenario developed tested D-T, showing...
Abstract Changes in global and edge plasma parameters ( H 98(y,2) , dimensionless collisionality ν * core density peaking, separatrix n e,sep ) with variations the D 2 fueling rate divertor configuration are unified into a single trend when mapped to ⟨ T e,ot ⟩, spatially averaged spectroscopically derived outer target electron temperature. Dedicated JET ITER-like wall (JET-ILW) experiments combination an extended JET-ILW database of unseeded low-triangularity H-mode plasmas spanning wide...
Abstract A sequence of fuel recovery methods was tested in JET, equipped with the ITER-like beryllium main chamber wall and tungsten divertor, to reduce plasma deuterium concentration less than 1% preparation for operation tritium. This also a key activity regard refining clean-up strategy be implemented at end 2nd DT campaign JET (DTE2) assess tools that are envisaged mitigate tritium inventory build-up ITER. The began 4 days baking 320 °C, followed by further which Ion Cyclotron Wall...
Abstract The required heating power, <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:mrow> <mml:msub> <mml:mi>P</mml:mi> <mml:mi>LH</mml:mi> </mml:mrow> </mml:msub> </mml:math> , to access the high confinement regime (H-mode) in tritium containing plasmas is investigated JET with ITER-like wall at a toroidal magnetic field of <mml:mi>B</mml:mi> <mml:mi>t</mml:mi> <mml:mo>=</mml:mo> <mml:mn>1.8</mml:mn> T and plasma current <mml:mi>I</mml:mi>...
A novel technique for sawteeth control in tokamak plasmas using ion-cyclotron resonance heating (ICRH) has been developed the JET-ILW tokamak.Unlike previous ICRH methods, that explored destabilization of internal kink mode when radio-frequency (RF) wave absorption was placed near q=1 surface, presented here consists stabilizing as fast possible by applying power centrally and subsequently induce a sawtooth crash switching it off at appropriate instant.The validation this method L-mode...
New experiments at JET with the ITER like wall show for first time that ITER-relevant low field side resonance harmonic ICRH can be used to control sawteeth have been initially lengthened by fast particles.In contrast previous [J.P. Graves et al, Nature Communs 3, 624 (2012)] high sawtooth undertaken JET, it is found of L-mode plasmas controlled less accurate alignment between layer and inversion radius.This advantage, as well discovery shortened various antenna phasings, including dipole,...
Measurements of the ion currents to and plasma conditions at low-field side (LFS) divertor target plate in low-confinement mode plasmas JET ITER-like wall materials configuration show that core density required detach LFS is independent hydrogenic species protium, deuterium tritium, a 40 %/60 % deuterium–tritium mixture. This observation applies with strike line connected horizontal part chosen because its superior diagnostic coverage. The finding operational status cryogenic pump. electron...