A5084472689- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Particle accelerators and beam dynamics
- Ionosphere and magnetosphere dynamics
- Plasma Diagnostics and Applications
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Plasma Applications and Diagnostics
- Laser Design and Applications
- Gyrotron and Vacuum Electronics Research
- Metal Alloys Wear and Properties
- Nuclear Physics and Applications
- Radioactive contamination and transfer
- Radioactivity and Radon Measurements
- Atomic and Molecular Physics
- Electromagnetic Launch and Propulsion Technology
- Solar and Space Plasma Dynamics
- Nuclear physics research studies
- Ophthalmology and Eye Disorders
- Metallurgy and Material Science
- Surface Treatment and Coatings
- Physics of Superconductivity and Magnetism
- Electrostatic Discharge in Electronics
- Muon and positron interactions and applications
Culham Science Centre
2014-2024
Culham Centre for Fusion Energy
2012-2024
United Kingdom Atomic Energy Authority
2007-2024
Technical University of Sofia
2023-2024
Linguistics University of Nizhny Novgorod
2021
Max Planck Society
2001-2017
Max Planck Innovation
2017
CEA Cadarache
2005-2012
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2005-2012
Southwestern Institute of Physics
2011
Abstract The ASDEX Upgrade (AUG) programme is directed towards physics input to critical elements of the ITER design and preparation operation, as well addressing issues for a future DEMO design. Since 2015, AUG equipped with new pair 3-strap ICRF antennas, which were designed reduction tungsten release during operation. As predicted, factor two on ICRF-induced W plasma content could be achieved by sheath voltage at antenna limiters via compensation image currents central side straps in...
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 STEP is a spherical tokamak prototype power plant that being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models optimise fusion performance subject satisfying various physics and engineering constraints. A modelling workflow, including integrated core modelling, MHD stability analysis, SOL pedestal coil set free boundary equilibrium solvers, whole design, has been developed specify parameters develop viable scenarios. model JETTO...
The evolution of the JET high performance hybrid scenario, including central accumulation tungsten (W) impurity, is reproduced with predictive multi-channel integrated modelling over multiple confinement times using first-principle based core transport models.8 channels ( , ) are modelled predictively, self-consistent sources, radiation and magnetic equilibrium, yielding a system non-linearities: This can reproduce observed radiative temperature collapse after several times.W transported...
This paper summarizes the physical principles behind novel three-ion scenarios using radio frequency waves in ion cyclotron range of frequencies (ICRF). We discuss how to transform mode conversion electron heating into a new flexible ICRF technique for and fast-ion generation multi-ion species plasmas. The theoretical section provides practical recipes selecting plasma composition realize scenarios, including two equivalent possibilities choice resonant absorbers that have been identified....
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 In magnetic fusion devices, error field (EF) sources, spurious perturbations, need to be identified and corrected for safe stable (disruption-free) tokamak operation. Within Work Package Tokamak Exploitation RT04, a series of studies have been carried out test the portability novel non-disruptive method, designed tested in DIII-D (Paz-Soldan et al 2022 Nucl. Fusion 62 126007), perform an assessment model-based EF control strategies towards their applicability ITER. this paper,...
STEP is a spherical tokamak prototype power plant that being designed to demonstrate net electric power. The design phase involves the exploitation of plasma models optimise fusion performance subject satisfying various physics and engineering constraints. A modelling workflow, including integrated core modelling, MHD stability analysis, SOL pedestal coil set free boundary equilibrium solvers, whole design, has been developed specify parameters develop viable scenarios. model JETTO used...
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 UK’s Spherical Tokamak for Energy Production (STEP) reactor design program has recently taken the decision to use exclusively microwave-based heating and current drive (HCD) actuators its concepts. This is based on a detailed assessment considering all viable HCD concepts, covering grid plasma efficiency, physics applications, technology maturity, integration, maintenance, costs. Of two microwave techniques: Electron Cyclotron (EC) Bernstein Wave (EBW), EC was deemed lowest risk EBW...
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 Building on prior analysis of ASDEX Upgrade (AUG) experiments (Henderson et al 2023 Nucl. Fusion 63 086024), this study compares simple analytical formula predictions for divertor detachment onset and reattachment timescales in JET experiments. Detachment primarily scales with neutral pressure, impurity concentration, power directed to the targets, machine size, integral perpendicular decay length. experiments, focusing seeding mixtures Ne Ar, align predictions. Radiation...
The electron heat transport is investigated in ASDEX Upgrade using cyclotron heating (ECH) combining steady-state and power modulation schemes. Experiments which the flux has been varied confinement region while edge was kept constant were performed. They demonstrate that ∇ Te Te/Te can be by a factor of 3 2, respectively. allow detailed determination characteristics comparing data with modelling. analyses clearly show existence threshold (∇ Te/Te)crit above increases. Both experiments agree...
A new ITER-relevant lower hybrid current drive (LHCD) launcher, based on the passive-active-multijunction (PAM) concept, was brought into operation Tore Supra tokamak in autumn 2009. The PAM launcher concept designed view of ITER to allow efficient cooling waveguides, as required for long pulse operation. In addition, it offers low power reflection close cut-off density, which is very attractive ITER, where large distance between plasma and wall may bring density front values. first...
Predictability of burning plasmas is a key issue for designing and building credible future fusion devices. In this context, an important effort physics understanding guidance being carried out in parallel to JET experimental campaigns H D by performing analyses modelling towards improvement the DT optimization JET-DT neutron yield born alpha particle physics. Extrapolations from recent experiments using maximum power available have been performed including some most sophisticated codes...
Dedicated experiments were conducted in mixed H-D plasmas JET to demonstrate the efficiency of 3-ion ICRF scheme for plasma heating, relying on injected fast NBI ions as resonant ion species.Strong core localization RF power deposition close vicinity ion-ion hybrid layer was achieved, resulting an efficient generation energetic D ions, strong enhancement neutron rate and observation Alfvénic modes.A consistent physical picture that emerged from a range fast-ion measurements at JET, including...
A new deuterium-tritium experimental, DTE2, campaign has been conducted at the Joint European Torus (JET) between August 2021 and late December 2021. Motivated by significant enhancements in past decade JET, such as ITER-like wall enhanced auxiliary heating power, achieved a fusion energy world record performed broad range of fundamental experiments to inform ITER physics scenarios operations. New capabilities area product measurements nuclear diagnostics were available result long...
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...
The achievement of a steady ELMy H-mode phase with high ion temperature, but without gradual rise in plasma radiation, has been crucial point to establish performance scenarios JET ITER-like-wall plasmas. Indeed, radiation events, due the release Z impurities, such as Nickel and Copper, W sputtered from divertor, can strongly reduce power crossing separatrix slow ELMs dynamics, thus inducing H L transition. In particular, baseline plasmas, because outward neoclassical transport [A.R. Field...