A5036628326- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Advanced Chemical Physics Studies
- Atomic and Molecular Physics
- Nuclear reactor physics and engineering
- Laser Design and Applications
- Particle physics theoretical and experimental studies
- X-ray Spectroscopy and Fluorescence Analysis
- High-Energy Particle Collisions Research
- Mass Spectrometry Techniques and Applications
- Laser-induced spectroscopy and plasma
- Electric Power Systems and Control
- Pulsed Power Technology Applications
- Solar and Space Plasma Dynamics
- Advanced Data Storage Technologies
Culham Centre for Fusion Energy
2021-2024
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
Forschungszentrum Jülich
2024
École Polytechnique Fédérale de Lausanne
2009
Drake University
2008
Flinders University
2008
Abstract Progress in physics understanding and theoretical model development of plasma transport confinement (TC) the ITPA TC Topical Group since publication ITER Physics Basis (IPB) document (Doyle et al 2007 Nucl. Fusion 47 S18) was summarized focusing on contributions to burning prediction control. This paper provides a general streamlined overview advances that were mainly led by joint experiments activities for last 15 years (see JEX/JA table appendix). starts with scientific strategy...
Abstract In JET deuterium-tritium (D-T) plasmas, the fusion power is produced through thermonuclear reactions and between thermal ions fast particles generated by neutral beam injection (NBI) heating or accelerated electromagnetic wave in ion cyclotron range of frequencies (ICRFs). To complement experiments with 50/50 D/T mixtures maximizing reactivity, a scenario dominant non-thermal reactivity has been developed successfully demonstrated during second campaign DTE2, as it was predicted to...
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 The multi-machine International Tokamak Physics Activity (ITPA) Global H-mode Confinement Database has been upgraded with new data from JET the ITER-like wall and ASDEX Upgrade full tungsten wall. This paper describes database presents results of regression analysis to estimate global energy confinement scaling in plasmas using a standard power law. Various subsets are considered, focusing on type divertor materials, regime (all H-modes, ELMy H or ELM-free) constraints. Apart...
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 After the second Deuterium–Tritium Campaign (DTE2) in JET tokamak with ITER-Like Wall (ILW) and full tritium campaigns that preceded followed after DTE2, a sequence of fuel recovery methods was applied to promote removal from wall components. The started several days baking main chamber walls at 240 °C 320 °C. Subsequently, superimposed Ion-Cyclotron Conditioning (ICWC) Glow Discharge (GDC) cleaning cycles deuterium. Diverted plasma operation deuterium different strike point...
Abstract In the paper we present an overview of interpretive modelling a database JET-ILW 2021 D-T discharges using TRANSP code. The main aim is to assess our capability computationally reproducing fusion performance various plasma scenarios different external heating and mixtures, understand driving mechanisms. We find that simulations confirm general power-law relationship between increasing power output, which supported by absolutely calibrated neutron yield measurements. A comparison...
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 JET experiments using the fuel mixture envisaged for fusion power plants, deuterium and tritium (D–T), provide a unique opportunity to validate existing D–T prediction capabilities in support of future device design operation preparation. The 2021 experimental campaign has achieved powers sustained over 5 s ITER-relevant conditions i.e. with baseline or hybrid scenario full metallic wall. In preparation campaign, extensive predictive modelling was carried out several assumptions...
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
Abstract Burning reactor plasmas will be self-heated by fusion born alpha particles from deuterium-tritium reactions. Consequently, a thorough understanding of the confinement and transport DT-born is necessary to maintain plasma self-heating. Measurements fast ion losses provide direct means monitor particle confinement. JET’s 2021–2022 second experimental DT-campaign offers burning scenarios with advanced loss diagnostics for first time in nearly 25 years. Coherent non-coherent were...
Abstract The fusion reaction between deuterium and tritium, D ( T,n ) 4 He is the main source of energy in future thermonuclear reactors. Alpha-particles -ions) born with an average 3.5 MeV transferring to thermal plasma during their slowing down, should provide self-sustained D–T burn. adequate confinement α -particles essential efficient heating bulk steady burning a reactor plasma. That why fusion-born -particle studies have been priority task second experiments (DTE2) on Joint European...
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...
The generic problem of how, in a turbulent plasma, the experimentally relevant conditions particle flux very close to null are achieved, despite presence strong heat fluxes, is addressed. Nonlinear gyrokinetic simulations plasma turbulence tokamaks reveal complex dependence as function spatial scale and velocity space collisionality increased. At experimental values collisionality, found null, agreement with experiment, due balance between inward outward contributions at small large scales,...
Abstract In the JET DTE2 deuterium-tritium campaign, neutron diagnostics were employed to measure 14 MeV neutrons originating from D(T,n) 4 He reactions. discharge 99965, a diamond matrix detector (KM14) and magnetic proton recoil (MPRu) with vertical an oblique line-of-sight used, respectively. At timepoints of interest, significant decrease in expected diagnostic signals can be observed as electromagnetic wave heating ion cyclotron range frequencies (ICRF) is switched off. Utilizing only...
Abstract This work studies the influence of radio frequency (RF) waves in ion cyclotron resonance heating (ICRH) range frequencies on fusion alphas during recent JET D-T campaign. Fusion from reactions are created with energies about 3.5 MeV and therefore have significant Doppler shifts enabling synergistic interactions between them RF at a broad frequencies, including ones foreseen for future machines ITER (Schneider et al 2021 Nucl. 61 126058) SPARC (Creely 2020 J. Plasma Phys. 86...
Abstract In the JET DTE2 campaign a new method was successfully tested to detect heating of bulk electrons by α-particles, using dynamic response electron temperature T e modulation ion cyclotron resonance (ICRH). A fundamental deuterium (D) ICRH scheme applied tritium-rich hybrid plasma with D-neutral beam injection (NBI). The i and accelerated deuterons leads modulated α -heating large delay respect other terms. significant phase ∼40° is measured between central , which can only be...
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...
Beam-target reactions are responsible for a substantial fraction of the fusion power generated in D-T plasmas JET-ILW (Be/W-wall), with ion temperatures 10-12keV and large neutral-beam injection (NBI) power.It is known that injecting D beam ions energies ~100-150keV T-rich has larger potential beam-target than 50:50 D:T plasmas, but such scenario was never developed past experiments performed JET-C (Carbon-wall) TFTR 90's.On top intrinsic advantages using beams neutron production,...
To produce fusion reactions efficiently, thermonuclear plasmas have to reach extremely high temperatures, which is incompatible with their coming into contact material surfaces. Confinement of using magnetic fields has progressed significantly in the last years, particularly tokamak configuration. Unfortunately, all devices, and metallic ones, are plagued by catastrophic events called disruptions. Many disruptions preceded anomalies radiation patterns, ITER-relevant scenarios. These specific...