A5041271400- Magnetic confinement fusion research
- Fusion materials and technologies
- Ionosphere and magnetosphere dynamics
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Plasma Diagnostics and Applications
- Solar and Space Plasma Dynamics
- High-Energy Particle Collisions Research
- Tropical and Extratropical Cyclones Research
- Seismic Imaging and Inversion Techniques
- Fault Detection and Control Systems
- Geological Modeling and Analysis
- Seismic Waves and Analysis
- Particle physics theoretical and experimental studies
- Nuclear Materials and Properties
- Semiconductor materials and devices
- Marine and fisheries research
- Reservoir Engineering and Simulation Methods
- Anomaly Detection Techniques and Applications
- Muon and positron interactions and applications
- Advanced Data Storage Technologies
- Nuclear Physics and Applications
- Coastal and Marine Dynamics
Culham Science Centre
2010-2024
Culham Centre for Fusion Energy
2009-2024
United Kingdom Atomic Energy Authority
2022-2024
CEA Cadarache
2024
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2024
Royal Military Academy
2020
Saudi Aramco (United States)
2019
Cardno (United Kingdom)
2011
Falmouth University
2010
Experiments have been performed on MAST using both external ( n = 1, 2) and internal 3) resonant magnetic perturbation (RMP) coils. ELM suppression has not achieved even though vacuum modelling shows that either set of coils can produce a region (ΔΨ pol > 0.17), for which the Chirikov parameter is greater than wider correlated with in DIII-D. Although complete achieved, application RMPs triggered ELMs free H-mode periods increased frequency regularly ELM-ing discharges 2, 3). In addition,...
Electron Bernstein wave (EBW) assisted plasma current start-up has been demonstrated for the first time in a tokamak. It was shown that currents up to 17 kA can be generated non-inductively by 100 kW of RF power injected. With optimized vertical field ramps, 33 have achieved without use solenoid flux. is formation and generation are governed predominantly EBW drive. Experimental results consistent with ray-tracing quasilinear Fokker–Planck modelling.
The dependences of energy confinement on plasma current and toroidal magnetic field have been investigated in the MAST spherical tokamak H-mode plasmas. Multivariate fits show that dependence time Ip is weaker than linear while BT stronger linear, contrast to conventional scalings. These also confirmed by single parameter scans. Transport analysis indicates strong scaling could possibly be explained q ν* heat diffusivity comparison with tokamaks.
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 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 This paper presents a study on the dependence of ion temperature stiffness plasma main isotope mass in JET ITER-like wall and C discharges. To this aim, database H, D T shots is analyzed, including new dedicated shots, comparing experiments with lower higher power injected by NBI system. In order to characterize turbulence mass, three these discharges (two one D) same external heating scheme are studied detail interpreted gyrokinetic linear nonlinear simulations. The analysis...
This paper presents a description of the spatial and temporal structure edge-localized modes (ELMs) observed in MAST tokamak. Filamentary enhancements visible light are on photographic images plasma obtained during ELMs. Comparisons with simulations show that these filaments consistent following field lines at outboard edge plasma. The toroidal mode number has been extracted from study discrete peaks ion saturation current recorded by mid-plane reciprocating probe. A time delay respect to...
A combination of recently installed state-of-the-art imaging and profile diagnostics, together with established plasma simulation codes, are providing for the first time on Mega Ampère Spherical Tokamak (MAST) tools required studying confinement transport, from core through to edge scrape-off-layer (SOL). The H-mode transport barrier is now routinely turned off using a poloidally localized fuelling fine balancing X-points. Theory, supported by experiment, indicates that radial electric field...
Edge localized mode (ELM) characteristics in a large spherical tokamak (ST) with significant auxiliary heating are explored. High confinement is achieved mega ampere (MAST) at low ELM frequencies even though the ELMs exhibit many type III characteristics. These associated reduction pedestal density but no change temperature or profile, indicating that energy convected from region into scrape-off layer. Power to targets during an arrives predominantly field outboard side. effluxes observed up...
In the past 10 years, vertical seismic profiles (VSPs) have played an increasingly important role in identifying and delineating situ layers. Such VSPs usually recorded P-wave data. Three‐component shear wave trains carry three or four times more information about source structure of rocks along raypath than equivalent train so, principle, shear‐wave should be a particularly valuable technique for examining
Major developments on the Mega Amp Spherical Tokamak (MAST) have enabled important advances in support of ITER and physics basis a spherical tokamak (ST) based component test facility (CTF), as well providing new insight into underlying physics. For example, L–H transition studies benefit from high spatial temporal resolution measurements pedestal profile evolution (temperature, density radial electric field) stability edge current has been inferred motional Stark effect measurements. The...
JET’s frequency-modulated continuous wave (FMCW) reflectometers have been operating well with the current design since 2005, and density profiles automatically calculated intershot then. However, had long suffered from several shortcomings: poor agreement other diagnostics, sometimes inappropriately moving radially by centimeters, elevated levels of radial jitter, persistent wriggles (strong unphysical oscillations). In this research, techniques are applied to reflectometry data analysis,...
The low aspect ratio of the mega amp spherical tokamak (MAST) allows differentiation between different forms H-mode threshold scaling. With optimized fuelling using inboard puffing, and a connected double null divertor (DND) magnetic configuration, power data lie about 1.7 times higher than recent scaling laws. Slight configuration changes, order ion Larmor radius, around DND significantly influence access. confinement in discharges with frequency edge localized modes (ELMs) is generally...
This paper quantifies the particle confinement of pellet-fuelled plasmas as measured in Mega Ampere Spherical Tokamak. The dataset is restricted mostly to neutral beam heated H-mode and shallow pellets launched from high-field side. It shown that pellet deposition can be explained only by invoking ∇ B drift ablatant. creates a zone with positive density gradient increased temperature gradient. Simulations show these changes could increase level micro-turbulence thus enhance further...
Edge localized mode (ELM) control has been investigated on MAST with a set of in-vessel coils producing n = 3 perturbations. In spite broad enough region where the Chirikov parameter is above 1, according to criterion employed for design ITER ELM coils, no effect was seen type I ELMs. The behaviour different from that in DIII-D this respect. do have an effect, however, Ohmic L-mode plasmas and just L–H transition. former, they induce density pump-out, modify turbulence characteristics edge...
Several improvements to the MAST plant and diagnostics have facilitated new studies advancing physics basis for ITER DEMO, as well future spherical tokamaks (STs). Using increased heating capabilities P NBI ⩽ 3.8 MW H-mode at I p = 1.2 MA was accessed showing that energy confinement on scales more weakly with strongly B t than in IPB98( y , 2) scaling. Measurements of fuel retention shallow pellets extrapolate an particle throughput 70% its original designed total capacity. The anomalous...
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 set of experiments was carried out in JET ILW (Joint European Torus with ITER-Like Wall) L-mode plasmas order to study the effects light impurities on core ion thermal transport. N puff ...
This paper presents results of JET ITER-like wall L-mode experiments in hydrogen and deuterium (D) plasmas, dedicated to the study isotope dependence ion heat transport by determination critical gradient stiffness varying cyclotron resonance heating power deposition. When no strong role fast ions plasma core is expected, main difference between two plasmas determined edge behavior consistent with a gyro-Bohm scaling. (and pressure) increased, addition region, also shows substantial changes....
Abstract For more than a decade, an unprecedented predict-first activity has been carried in order to predict the fusion power and provide guidance second Deuterium–Tritium (D–T) campaign performed at JET 2021 (DTE2). Such provided framework for broad model validation development towards D–T operation. It is shown that it necessary go beyond projections using scaling laws obtain detailed physics based predictions. Furthermore, mixing different modelling complexity promoting extended...
The pre-fusion power operation (PFPO) phase of ITER, as described in the ITER research plan with Staged Approach2, includes both hydrogen (H) and helium (He) plasma operations. In preparation for PFPO, WEST JET ran He campaigns to study plasma-wall interactions a tungsten environment. included back-and-forth transition between H or deuterium (D) allowing assessment achievable content well accessible wall reservoirs respective species. changeovers tokamak pulses fixed divertor configuration....