A5088159869- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Laser-Plasma Interactions and Diagnostics
- Nuclear reactor physics and engineering
- Ionosphere and magnetosphere dynamics
- Particle accelerators and beam dynamics
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Laser-induced spectroscopy and plasma
- Nuclear Materials and Properties
- Fluid Dynamics and Turbulent Flows
- Solar and Space Plasma Dynamics
- Atomic and Molecular Physics
- Muon and positron interactions and applications
- Gas Dynamics and Kinetic Theory
- High-Energy Particle Collisions Research
- Distributed and Parallel Computing Systems
- Advanced Data Storage Technologies
- Advanced Sensor Technologies Research
- Non-Destructive Testing Techniques
- Advanced Measurement and Metrology Techniques
- Anomaly Detection Techniques and Applications
- Metallurgical Processes and Thermodynamics
- Particle Accelerators and Free-Electron Lasers
Culham Centre for Fusion Energy
2014-2024
Culham Science Centre
2015-2024
Forschungszentrum Jülich
2011-2024
United Kingdom Atomic Energy Authority
2022-2024
Royal Military Academy
2020
Joint European Torus
2015
ITER
2013
Fusion for Energy
2013
University of Lisbon
2010
University of Manchester
2010
Operation and exploitation of present future Tokamak reactors require advanced scenario modeling in order to optimize engineering parameters the design phase as well physics performance during phase. The simulation scenarios involves simultaneous different regions reactor, characterized by symmetries, predict quantities such particle energy confinement, fusion yield, power deposited on wall, wall load from fast particles. JINTRAC is a system 25 interfaced Tokamak-physics codes for integrated...
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...
Abstract The EMC3‐Eirene code is improved in many aspects. Ad hoc boundary conditions for intrinsic impurities at the SOL‐core interface are removed by implicitly coupling to a 1D core model. Non‐uniform cross‐field transport coefficients allowed new version. A particle splitting technique implemented improving Monte Carlo statistic low‐temperature ranges of most interest. Domain splitting, which was possible toroidal direction only, now feasible all three directions, facilitating mesh...
Recent experiments on JET have shown that type-I edge localized modes (ELMs) can be controlled by the application of static low n = 1 external magnetic perturbation fields produced four error field correction coils (EFCC) mounted far away from plasma between transformer limbs. When an with amplitude a few mT at (the normalized poloidal flux, ?, is larger than 0.95) applied during stationary phase ELMy H-mode plasma, ELM frequency rises ~30?Hz up to ~120?Hz. The energy loss per total stored...
At the TEXTOR tokamak an external resonant magnetic perturbation is applied with dynamic ergodic divertor to control edge transport properties. The approaches analyse impact of such a kind stochastization on apply mostly shell-like picture which includes dependence from field topology in radial direction only. In this paper multiple experimental evidence presented contrast these forms poloidally heterogenous layer characteristics are determined by alternating line behaviour. A thorough...
Experiments on JET with a carbon-fibre composite wall have explored the reduction of steady-state power load in an ELMy H-mode scenario at high Greenwald fraction ∼0.8, constant and close to L H transition. This paper reports systematic study due effect fuelling combination seeding over wide range pedestal density ((4–8) × 1019 m−3) detailed documentation divertor, main plasma conditions, as well comparative two extrinsic impurity nitrogen neon. It also impact overall behaviour, possible...
Abstract Results from three-dimensional modeling of plasma edge transport and plasma–wall interactions during application resonant magnetic perturbation (RMP) fields for control edge-localized modes in the ITER standard 15 MA Q = 10 H-mode are presented. The full 3D fluid kinetic neutral code EMC3-EIRENE is used modeling. Four characteristic perturbed topologies considered discussed with reference to axisymmetric case without RMP fields. Two field amplitudes at half ELM coil current...
Abstract In the initial stages of ITER operation, ELM mitigation systems need to be commissioned. This requires controlled flat-top operation in type-I ELMy H-mode regimes. Hydrogen or helium plasma discharges are used exclusively these ensure negligible production neutrons from fusion reactions. With expected higher L-H power threshold hydrogen and plasmas compared corresponding D D/T plasmas, it is uncertain whether available auxiliary sufficient operate stable H-mode. has been...
The first results of the Dynamic Ergodic Divertor in TEXTOR, when operating m/n=3/1 mode configuration, are presented. deeply penetrating external magnetic field perturbation this configuration increases toroidal plasma rotation. Staying below excitation threshold for m/n=2/1 tearing mode, rotation is always direction current, even if projection rotating opposite direction. observed consistent with a radial electric field, generated by an enhanced electron transport ergodic layers near...
A strong toroidal rotation braking has been observed in plasmas with application of an n = 1 magnetic perturbation field on the JET tokamak. Calculation results from momentum transport analysis show that torque induced by a global profile. The maximal value this is at plasma core region (ρ < 0.4) and it about half neutral beam injection torque. calculation shows mainly regime core, but close to transition between 1/ν regimes. neoclassical viscosity (NTV) regimes calculated. magnitude NTV...
The ITER baseline scenario, with 500 MW of DT fusion power and Q = 10, will rely on a Type I ELMy H-mode, ΔW 0.7 MJ mitigated edge localized modes (ELMs). Tungsten (W) is the material now decided for divertor plasma-facing components from start plasma operations. W atoms sputtered targets during ELMs are expected to be dominant source under partially detached conditions required safe operation. impurity concentration in core can dramatically degrade its performance lead potentially damaging...
Mitigation of type-I edge-localized modes (ELMs) was observed with the application an n = 2 field in H-mode plasmas on JET tokamak ITER-like wall (ILW). Several new findings ILW were identified and contrasted to previous carbon (C-wall) results for comparable conditions. Previous high collisionality C-wall saw little or no influence either 1 fields ELMs. However, recent observations show large ELMs a frequency ∼45 Hz replaced by high-frequency (∼200 Hz) small during field. With ILW,...
Tokamak operation with W PFCs is associated specific challenges for impurity control, which may be particularly demanding in the transition from stationary H-mode to L-mode. To address contr ...
The ITER baseline scenario, with 500 MW of DT fusion power and Q = 10, will rely on a Type I ELMy H-mode be achieved tungsten (W) divertor. W atoms sputtered from divertor targets during mitigated ELMs are expected to the dominant source in ITER. impurity concentration plasma core can dramatically degrade its performance lead potentially damaging disruptions. Understanding physics target due sputtering inter-ELMs is important helped by experimental measurements improved precision. It has...
The operational domain for active control of type-I edge localized modes (ELMs) with an n = 1 external magnetic perturbation field induced by the ex-vessel error correction coils on JET has been developed towards more ITER-relevant regimes high plasma triangularity, up to 0.45, normalized beta, 3.0, current 2.0 MA and q95 varied between 3.0 4.8. results ELM mitigation in triangularity plasmas show that frequency ELMs increased a factor 4 during application fields, while energy loss per ELM,...
Abstract The non-resonant magnetic braking effect induced by a non-axisymmetric perturbation is investigated on JET and TEXTOR. collisionality dependence of the torque n = 1, where toroidal mode number, generated error field correction coils observed. observed located mainly in plasma core (normalized radius ρ < 0.4) increases with decreasing collisionality. neoclassical viscosity (NTV) collisionless regime modelled using numerical solution bounce-averaged drift kinetic equation....
At JET the error field correction coils can be used to generate an n = 1 or 2 magnetic perturbation (Liang et al 2007 Plasma Phys. Control. Fusion 49 B581). Various experiments at have already been carried out investigate mitigation of ELMs by resonant perturbations (RMPs) 2010 Nucl. 50 025013, Liang 2011 51 073001). However, typical formation a secondary strike point (strike splitting) RMPs observed in other machines (Jakubowski Contrib. 701–7, Jakubowski 2004 44 S1–11, Nardon J. Mater. 415...
The EDGE2D-EIRENE code is applied for simulation of divertor detachment during matched density ramp experiments in high triangularity, L-mode plasmas both JET-Carbon (JET-C) and JET-ITER-Like Wall (JET-ILW). runs without drifts includes either C or Be as impurity, but not W, assuming that the W targets have been coated with via main chamber migration. simulations reproduce reasonably well observed particle flux raised JET-C JET-ILW can better match experimental in-out target power asymmetry...
ITER operations require effective fuelling of the core plasma for conditions in which neutral dynamics through scrape-off layer is expected to significantly affect efficiency gas penetration. On basis previous analysis stationary conditions, pellets are foreseen provide high-Q DT scenarios. In this paper we present a modelling study providing an estimate maximum density achievable with only various reference Dynamical integrated core-edge simulations phases H-mode discharges have been...
Recent studies dedicated to the characterisation of in-vessel dust in JET with new ITER-like wall (ILW) show that levels are orders magnitude lower compared latter stages carbon-wall (CW) period and decreasing operational time. Less than 1 g was recovered a recent inspection, more 200 material at end JET-CW life. inspection ILW shows low rates re-deposition only small areas damage type likely create particulate matter. Quantifiers from laser scattering techniques also indicate an order...
Experiments in the JET tokamak equipped with ITER-like wall (ILW) revealed that inner and outer target plate at location of strike points represent after one year operation intact tungsten (W) surfaces without any beryllium (Be) surface coverage. The dynamics near-surface retention, implantation, desorption recycling deuterium (D) divertor plasma discharges are determined by W plates. As plasma-facing components (PFCs) not actively cooled, temperature (Tsurface) is increasing exposure,...
Abstract In high confinement mode, highly shaped plasmas with edge localized modes in JET, and for heating power of 15–17 MW, the fluid code EDGE2D-EIRENE predicts transition to detachment assisted by nitrogen at low field side (LFS) target when more than 50% crossing separatrix between ELMs is radiated divertor chamber, i.e. ~4 MW. This observed both ITER-like wall (JET-ILW) carbon (JET-C) configurations consistent experimental observations within their uncertainty. these conditions, peak...