A5066731764- Magnetic confinement fusion research
- Fusion materials and technologies
- Superconducting Materials and Applications
- Ionosphere and magnetosphere dynamics
- Laser-Plasma Interactions and Diagnostics
- Particle accelerators and beam dynamics
- Nuclear reactor physics and engineering
- Plasma Diagnostics and Applications
- Nuclear Physics and Applications
- Solar and Space Plasma Dynamics
- Nuclear Materials and Properties
- Electrostatic Discharge in Electronics
- Plasma and Flow Control in Aerodynamics
- Nuclear Engineering Thermal-Hydraulics
- Meteorological Phenomena and Simulations
- Fluid Dynamics and Turbulent Flows
- Fault Detection and Control Systems
- Model Reduction and Neural Networks
- High-Energy Particle Collisions Research
- Laser-induced spectroscopy and plasma
- Metal and Thin Film Mechanics
- Lattice Boltzmann Simulation Studies
- Time Series Analysis and Forecasting
- Complex Systems and Time Series Analysis
- Quantum chaos and dynamical systems
Culham Centre for Fusion Energy
2015-2025
Culham Science Centre
2015-2024
United Kingdom Atomic Energy Authority
2007-2024
Royal Military Academy
2020
KTH Royal Institute of Technology
2004-2019
Czech Academy of Sciences, Institute of Plasma Physics
2019
University of York
2019
University of Strathclyde
2013
Japan Atomic Energy Agency
2012
TU Wien
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...
Abstract The ramp-up is a critical phase in the operations of Tokamak, during which engineering and physics aspects must be taken into account to ensure stability, minimize flux consumption avoid disruptions. Predicting phases faces challenges such as nonlinearity, uncertainty on boundary initial conditions changes magnetic equilibrium. Our work uses High-Fidelity Pulse Simulator (HFPS), Python workflow based JINTRAC. input output are machine code generic IMAS data format. HFPS predicts...
As part of the ITER Design Review and in response to issues identified by Science Technology Advisory Committee, physics requirements were reviewed as appropriate updated. The focus this paper will be on recent work affecting design with special emphasis topics near-term procurement arrangements. This describe results on: sensitivity studies, poloidal field coil requirements, vertical stability, effect toroidal ripple thermal confinement, material choice heat load for plasma-facing...
This paper is an overview of recent results relating to turbulent particle and heat transport, the triggering internal transport barriers (ITBs). The dependence pinch velocity on plasma parameters has been clarified compared with experiment. Magnetic shear collisionality are found play a central role. Analysis made progress along two directions: dimensionless scaling laws, which agree prediction for electrostatic turbulence, analysis modulation experiments, provide stringent test models....
The dependence of plasma transport and confinement on the main hydrogenic ion isotope mass is fundamental importance for understanding turbulent and, therefore, accurate extrapolations from present tokamak experiments, which typically use a single hydrogen isotope, to burning plasmas such as ITER, will operate in deuterium–tritium mixtures. Knowledge properties edge barrier formation species critical view initial, low-activation phase ITER operations or helium its implications subsequent...
Particle transport in magnetized plasmas is investigated with a fluid model of drift wave turbulence. An analytical calculation shows that magnetic field curvature and thermodiffusion drive an anomalous pinch. The driven pinch velocity consistent the prediction turbulence equipartition theory. flux found to be directed inward for small ratio electron ion pressure gradient, it reverses its sign when increasing this ratio. Numerical simulations confirm turbulent particle exists. It mainly by...
For the first time, scalings for density peaking in tokamaks are obtained from a database consisting of observations two devices, ASDEX Upgrade and JET. The investigation relies on an inversion method interferometer signals which grants consistent reconstructions despite differences geometries. By combining these correlations between physics parameters investigated their role determining reduced. Multiple regression analyses show that combined collisionality is most relevant parameter....
Recent developments in theory-based modelling of core heavy impurity transport are presented, and shown to be necessary for quantitative description present experiments JET ASDEX Upgrade. The treatment impurities is complicated by their large mass charge, which result a strong response plasma rotation or any small background electrostatic field the plasma, such as that generated anisotropic external heating. These forces lead poloidal asymmetries density, have recently been added numerical...
The scan of ion cyclotron resonant heating (ICRH) power has been used to systematically study the pump out effect central electron on impurities such as Ni and Mo in H-mode low collisionality discharges JET. transport parameters have measured by introducing a transient perturbation their densities via laser blow off technique. Without ICRH density profiles are typically peaked. application induces plasma centre (at normalized poloidal flux ρ = 0.2) an outward drift approximately proportional...
Quasilinear turbulent transport models are a successful tool for prediction of core tokamak plasma profiles in many regimes. Their success hinges on the reproduction local nonlinear gyrokinetic fluxes. We focus significant progress quasilinear model QuaLiKiz [C. Bourdelle et al. 2016 Plasma Phys. Control. Fusion 58 014036], which employs an approximated solution mode structures to significantly speed up computation time compared full linear solvers. Optimization dispersion relation algorithm...
This paper reports the progress made at JET-ILW on integrating requirements of reference ITER baseline scenario with normalized confinement factor 1, a pressure 1.8 together partially detached divertor whilst maintaining these conditions over many energy times. The 2.5 MA high triangularity ELMy H-modes are studied two different configurations D-gas injection and nitrogen seeding. power load reduction N seeding is reported. relationship between an increase in pedestal investigated....
The JET exploitation plan foresees D–T operations in 2020 (DTE2). With respect to the first campaign 1997 (DTE1), when was equipped with a carbon wall, experiments will be conducted presence of beryllium–tungsten ITER-like wall and benefit from an extended improved set diagnostics higher additional heating power (32 MW neutral beam injection + 8 ion cyclotron resonance heating). There are several challenges presented by new wall: general deterioration pedestal confinement; risk heavy...
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...
Abstract In this work the onset of tearing modes in termination phase plasma pulses on JET is investigated. It shown that broadening or shrinking current density profile, as a consequence core hollowing an edge cooling electron temperature strongly increases probability destabilizing 2/1 mode also absence external trigger (e.g. sawtooth crash). Two parameters are defined to highlight changes shape profile can lead MHD instabilities and empirical stability diagram introduced into space two...
New H-mode regimes with high confinement, low core impurity accumulation, and small edge-localized mode perturbations have been obtained in magnetically confined plasmas at the Joint European Torus tokamak. Such are achieved by means of optimized particle fueling conditions input power, current, magnetic field, which lead to a self-organized state strong increase rotation ion temperature decrease edge density. An interplay between plasma regions leads reduced turbulence levels outward...
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...
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.
A factor of 4 dimensionless collisionality scan H-mode plasmas in MAST shows that the thermal energy confinement time scales as . Local heat transport is dominated by electrons and consistent with global scaling. The neutron rate good agreement ν* dependence τE,th. gyrokinetic code GYRO indicates micro-tearing turbulence might explain such a trend. 1.4 safety These two scalings are on plasma current magnetic field. Weaker qeng stronger dependences compared IPB98y2 scaling could be favourable...
Self-consistent transport simulation of ITER scenarios is a very important tool for the exploration operational space and scenario optimisation. It also provides an assessment compatibility developed (which include fast transient events) with machine constraints, in particular poloidal field (PF) coil system, heating current drive (H&CD), fuelling particle energy exhaust systems. This paper discusses results predictive modelling all reference variants using two suite linked equilibrium...
A pedestal prediction model Europed is built on the existing EPED1 by coupling it with core transport simulation using a Bohm-gyroBohm to self-consistently predict JET-ILW power scan for hybrid plasmas that display weaker degradation than IPB98(y, 2) scaling of energy confinement time. The weak reproduced in coupled core-pedestal simulation. further tested 3.0 MA plasma highest stored achieved so far, giving within error margins measured experimental value. density based neutral penetration...
Scenario modelling for the demonstration fusion reactor (DEMO) has been carried out using a variety of simulation codes.Two DEMO concepts have analysed: pulsed tokamak, characterised by rather conventional physics and technology assumptions (DEMO1) steady-state with moderately advanced (DEMO2).Sensitivity to impurity concentrations, radiation, heat transport models investigated.For DEMO2, impact current driven non-inductively Neutral Beams studied full MonteCarlo simulations fast ion...
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 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...