A5065282294- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Nuclear reactor physics and engineering
- Laser-Plasma Interactions and Diagnostics
- Nuclear Materials and Properties
- Particle accelerators and beam dynamics
- Solar and Space Plasma Dynamics
- Particle Dynamics in Fluid Flows
- Nuclear Physics and Applications
- Combustion and Detonation Processes
- Advanced Data Storage Technologies
- Plasma Diagnostics and Applications
- High-Energy Particle Collisions Research
- Nuclear Engineering Thermal-Hydraulics
- Plasma and Flow Control in Aerodynamics
- Astro and Planetary Science
- Generative Adversarial Networks and Image Synthesis
- Atmospheric and Environmental Gas Dynamics
- Fire effects on ecosystems
- Distributed and Parallel Computing Systems
- Advanced X-ray and CT Imaging
- Advanced X-ray Imaging Techniques
- X-ray Spectroscopy and Fluorescence Analysis
Royal Military Academy
2020
Culham Centre for Fusion Energy
2013-2020
Culham Science Centre
2012-2019
University of Liverpool
2019
University of Cagliari
2019
University of Rome Tor Vergata
2010-2017
United Kingdom Atomic Energy Authority
2017
National Agency for New Technologies, Energy and Sustainable Economic Development
2010-2015
Max Planck Innovation
2012
Max Planck Society
2012
Disruptions are a major operational concern for next generation tokamaks, including ITER.They may generate excessive heat loads on plasma facing components, large electromagnetic forces in the machine structures and several MA of multi-MeV runaway electrons.A more complete understanding processes methods to suppress them is necessary ensure safe reliable operation future tokamaks.Runaway electrons were studied at JET-ILW showing that their dependencies (accelerating electric field, avalanche...
The three-dimensional plasma boundary displacements induced by applied non-axisymmetric magnetic perturbations have been measured in ASDEX Upgrade, DIII-D, JET, MAST and NSTX. arising from resonant (RMPs) are up to ±5% of the minor radius present-day machines. Good agreement can be found between different experimental measurements a range models—be it vacuum field line tracing, ideal MHD equilibrium modelling, or nonlinear amplification. various with predictions these models is presented,...
Abstract L to H transition studies at JET have revealed an n = 0, m 1 magnetic oscillation starting immediately the (called M-mode for brevity). While is present a weak ELM-less H-mode regime obtained, with clear increase of density and electron temperature pedestal. It intermediate state between H-mode. In ICRH heated plasmas or low NBI mode pedestal can remain steady (with small oscillations) duration heating phase, order 10 s more. The axisymmetric has period ~0.5–2 ms, poloidal number 1:...
The pedestal structure of type I ELMy H-modes has been analysed for JET-ILW.The electron pressure width is independent ρ* and increases proportionally to √β pol,PED .Additional broadening the observed, at constant β , with increasing ν* and/or neutral gas injection contribution atomic physics effects in setting cannot as yet be ruled out.Neutral penetration alone does not determine shape edge density profile ratio temperature scale lengths transport barrier region, η e order 1.5-2.The...
Four numerical codes are employed to investigate the dynamics of scrape-off layer filaments in tokamak relevant conditions. Experimental measurements were taken MAST device using visual camera imaging, which allows evaluation perpendicular size and velocity filaments, as well combination density temperature associated with perturbation. A new algorithm based on light emission integrated along field lines position filament is developed ensure that it properly detected tracked. The found have...
A 60 kV neutral lithium diagnostic beam probes the edge plasma of JET for measurement electron density profiles. This paper describes recent enhancements setup, new procedures calibration and protection measures ion gun during massive gas puffs disruption mitigation. New light splitting optics allow in parallel emission measurements with a double entrance slit CCD spectrometer (spectrally resolved) interference filter avalanche photodiode camera (fast fluctuation studies).
Future devices like JT-60SA, ITER and DEMO require quantitative predictions of pedestal density temperature levels, as well inter-ELM ELM divertor heat fluxes, in order to improve global confinement capabilities while preventing erosion/melting the planning future experiments. Such can be obtained from dedicated models EPED, non-linear MHD codes JOREK, for which systematic validation against current experiments is necessary. In this paper, we show progress JOREK code using JET simulations....
Abstract This work presents a detailed characterisation of the MAST Scrape Off Layer in L-mode. Scans line averaged density, plasma current and toroidal magnetic field were performed. A comprehensive integrated study SOL was allowed by use wide range diagnostics. In agreement with previous results, an increase density induced broadening midplane profile. not correlated divertor detachment, as confirmed systematic target ion flux decrease emission. Also, no clear correlation is found neutral...
Three dimensionless scans in the normalized Larmor radius ρ*, collisionality ν* and plasma pressure β have been performed JET with ITER-like wall (JET-ILW).
Activated dust mobilization during a Loss of Vacuum Accident (LOVA) is one the safety concerns for International Thermonuclear Experimental Reactor (ITER). Intense thermal loads in fusion devices occur plasma disruptions, edge localized modes and vertical displacement events. They will result macroscopic erosion facing materials consequent accumulation activated into ITER vacuum vessel (VV). These kinds events can cause leakage outside VV that represents high radiological risk workers...
Many measurements are required to control thermonuclear plasmas and fully exploit them scientifically. In the last years JET has shown potential generate about 50 GB of data per shot. These amounts require more sophisticated analysis methodologies perform correct inference various techniques have been recently developed in this respect. The present paper covers a new methodology extract mathematical models directly from without any priori assumption their expression. approach, based on...
The extrapolation of the energy confinement time to next generation devices has been investigated both theoretically and experimentally for several decades in tokamak community. Various scaling expressions have proposed using dimensional dimensionless quantities. They are all based on assumption that scalings power law form. In this paper, an innovative methodology is extract tokamaks directly from experimental databases, without any previous about mathematical form scalings. approach obtain...
A subset of JET ITER-like wall (ILW) discharges, combining electron density and temperature as well divertor heat flux measurements, has been collected for the validation non-linear magnetohydrodynamic (MHD) simulations edge-localised-modes (ELMs). This permits a quantitative comparison simulation results against experiments, which is required predicted ELM energy losses fluxes in future tokamaks like ITER. paper presents first such comparison, gives perspective what will be necessary to...
The results of TRANSP simulations neutron count rate profiles measured by a collimated flux monitor–neutron camera (NC)—for different plasma scenarios on MAST are reported. In addition, the effect various parameters emission is studied means simulation. fast ion redistribution and losses due to fishbone modes, which belong wider category energetic particle observed NC modelled in TRANSP.
Abstract The Mega Ampère Spherical Tokamak (MAST) programme is strongly focused on addressing key physics issues in preparation for operation of ITER as well providing solutions DEMO design choices. In this regard, MAST has provided results understanding and optimizing H-mode confinement, operating with smaller edge localized modes (ELMs), predicting handling plasma exhaust tailoring auxiliary current drive. all cases, the high-resolution diagnostic capability complemented by sophisticated...
Abstract In this paper, a refined set of statistical techniques is developed and then applied to the problem deriving scaling law for threshold power access H-mode confinement in tokamaks. This methodology 2010 version ITPA International Global Threshold Data Base v6b(IGDBTHv6b). To increase engineering operative relevance results, only macroscopic physical quantities, measured vast majority experiments, have been considered as candidate variables models. Different principled methods, such...
The power threshold (PThresh) to access the H-mode in tokamaks remains a subject of active research, because up now no theoretical relation has proved be general enough reliably interpret L–H transition. Over last few decades, much effort therefore been devoted deriving empirical scalings, assuming 'a priori' power-law model structure. In this paper, an scaling PThresh without any priori assumption about structure, i.e. functional form, is derived. Symbolic regression via genetic programming...
At the tokamak Joint European Torus (JET), electron cyclotron emission spectra in O-mode and X-mode polarisations are diagnosed simultaneous absolute terms for several harmonics with two Martin-Puplett interferometers. From second harmonic range polarisation, temperature profile can be deduced outboard side (low magnetic field strength) of JET but only some parts inboard (high strength). This spatial restriction bypassed, if a cutoff is not present inside plasma waves first range. Then, from...