R. Henriques
A5044524308- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Particle accelerators and beam dynamics
- High-Energy Particle Collisions Research
- Ionosphere and magnetosphere dynamics
- Particle physics theoretical and experimental studies
- Experimental Learning in Engineering
- Nuclear Physics and Applications
- Nuclear reactor physics and engineering
- Magnetic Field Sensors Techniques
- Experimental and Theoretical Physics Studies
- Cloud Computing and Remote Desktop Technologies
- Electrowetting and Microfluidic Technologies
- Particle Detector Development and Performance
- Dark Matter and Cosmic Phenomena
- Computational Physics and Python Applications
- Anomaly Detection Techniques and Applications
- Solar and Space Plasma Dynamics
- Quantum Chromodynamics and Particle Interactions
- Electron and X-Ray Spectroscopy Techniques
- Network Security and Intrusion Detection
- Congenital Anomalies and Fetal Surgery
University of Lisbon
2015-2024
Culham Science Centre
2021-2024
United Kingdom Atomic Energy Authority
2021-2024
Institut de Recherche sur la Fusion par Confinement Magnétique
2024
CEA Cadarache
2024
Culham Centre for Fusion Energy
2021-2023
University College Cork
2023
Instituto de Engenharia de Sistemas e Computadores Investigação e Desenvolvimento
1994-2022
Instituto Superior de Tecnologias Avançadas
2018-2022
Instituto Superior Técnico
2012-2022
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...
Abstract As part the DTE2 campaign in JET tokamak, we conducted a parameter scan T and D-T complementing existing pulses H D. For different main ion masses, type-I ELMy H-modes at fixed plasma current magnetic field can have pedestal pressure varying by factor of 4 total changing from <mml:math xmlns:mml="http://www.w3.org/1998/Math/MathML" overflow="scroll"> <mml:msub> <mml:mi>β</mml:mi> <mml:mrow> <mml:mi mathvariant="normal">N</mml:mi> </mml:mrow> </mml:msub> <mml:mo>=</mml:mo>...
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 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 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
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 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>...
Abstract For its initial operational phase, ITER has until recently considered using non-nuclear hydrogen (H) or helium (He) plasmas to keep nuclear activation at low levels. To this end, the Tokamak Exploitation Task Force of EUROfusion Consortium carried out dedicated experimental campaigns in He on ASDEX Upgrade (AUG) and JET tokamaks 2022, with particular emphasis put ELMy H-mode operation plasma-wall interaction processes as well comparison H deuterium (D) plasmas. Both pure mixed +...
Abstract The heating power to access the high confinement mode (H-mode), P LH , scales approximately inversely with isotope mass of main ion plasma species as found in (protonic) hydrogen, deuterium and tritium plasmas many fusion facilities over last decades. In first dedicated L–H transition experiments at Joint European Torus (JET) tokamak facility ITER-like wall (ILW), threshold, was studied systematically pure hydrogen–tritium mixtures a magnetic field 1.8 T current 1.7 MA order assess...
We present a study of the power threshold for L–H transitions (PLH) in almost pure helium plasmas, obtained recent experiments at JET with an ITER-like wall (Be and W divertor). The most notable new result is that density which PLH minimum, , considerably higher than deuterium hydrogen plasmas. discuss possible implications ITER its pre-fusion operating phase.
Abstract Unusually high power loads on the beryllium limiter caused by neutral beam re-ionisation, and much cooler divertor target surfaces were observed during recent JET tokamak tritium campaign. As both phenomena are driven scrape-off layer (SOL) physics, SOL features of 72 H-mode discharges their deuterium references have been studied. The majority (70) had exponentially decaying profiles. plasmas to increased separatrix density collisionality compared references. This is associated with...
Abstract This article investigates the triggering of ELMs on JET by injection frozen pellets isotopes Hydrogen. A method is established to determine probability that a specific pellet triggers particular ELM. allows clear distinction between pellet-ELM pairs are very likely represent events and unlikely such an event. Based this, parameters most affect ability trigger have been investigated. It has found location important, with from vertical high field side showing much higher efficiency...
e-lab is a remote laboratory which provides the control of real physics experiments over internet. The robustness framework has allowed implementation new outside main physical laboratory, for instance in high schools and science centres. To reduce costs number maintenance interventions, simple hardware platform to access experiment, including video encoding streaming was developed Raspberry Pi computer. Such network implementations are presented this paper as case study hydrostatic...
The Heavy Ion Beam Diagnostic (HIBD) on the tokamak ISTTOK (Instituto Superior Técnico TOKamak) has been modified, in terms of signal conditioning, to measure local fluctuations neσ1,2(Te) product (plasma density times effective ionization cross-section) along minor diameter, 12 sample volumes range −0.7a &lt; r 0.7a, with a maximum delay time 1 μs. corresponding signals show high correlation magnetic Mirnov coils characteristic MHD frequency plasmas and enable identification tearing...
We report here on the recent developments in deconvolution of path integral effects for study MHD pressure-like fluctuations measured by Heavy Ion Beam Diagnostic. In particular, we develop improved methods to account and remove effect determination ionization generation factors, including double primary beam. test method using HIBD simulation code which computes real beam trajectories attenuations due electron impact any selected synthetic profiles plasma current, potential, temperature...
The tokamak ISTTOK havy ion beam diagnostic (HIBD) operates with a multiple cell array detector (MCAD) that allows for the plasma density and fluctuations measurements simultaneously at different sampling volumes across plasma. To improve capability of investigations, new detection system signal conditioning amplifier have been designed tested. improvements in MCAD design are presented which allow nearly complete suppression spurious background by applying biasing potential onto special...
The interaction between zonal flows and turbulence is a self-regulating mechanism. Understanding this crucial to control plasma confinement. Results presented in paper aim at understanding the conditions under which geodesic acoustic modes (GAMs) influence turbulent transport. This achieved by performing perturbative experiments where GAMs are stimulated externally controlled. Experiments on ISTTOK revealed that increasing GAM shear rate over its natural value leads reduction of transport an...